@article{kugel_measurements_1995,
	series = {Proceedings of the {Third} {International} {Symposium} on {Fusion} {Nuclear} {Technology}},
	title = {Measurements of tokamak fusion test reactor {D}-{T} radiation shielding efficiency},
	volume = {28},
	issn = {0920-3796},
	url = {http://www.sciencedirect.com/science/article/pii/0920379695900802},
	doi = {10.1016/0920-3796(95)90080-2},
	abstract = {Measurements of neutron and gamma dose-equivalents were performed in the test cell, at the outer test cell wall, in nearby work areas, and out to the nearest property lines at a distance of 180 m. Argon ionization chambers, moderated 3He proportional counters, and fission chamber detectors were used to obtain measurements of neutron and gamma dose-equivalents per D-T neutron during individual tokamak fusion test reactor (TFTR) discharges. These measured neutron and gamma D-T dose-equivalents per TFTR neutron characterize the effects of local variations in material density resulting from the complex asymmetric site geometry. The measured dose-equivalents per TFTR D-T neutron and the cumulative neutron production were used to determine that the planned annual TFTR neutron production of 1 × 1021 D-T neutrons is consistent with the design objective of limiting the total dose-equivalent at the property line, from all radiation sources and pathways, to less than 10 mrem per year.},
	urldate = {2016-11-25},
	journal = {Fusion Engineering and Design},
	author = {Kugel, H. W and Ascione, G and Elwood, S and Gilbert, J and Ku, L. -P and Levine, J and Rule, K and Azziz, N and Goldhagen, P and Hajnal, F and Shebell, P},
	month = mar,
	year = {1995},
	pages = {534--544},
	file = {ScienceDirect Snapshot:files/94/0920379695900802.html:text/html}
}

@book{lorraine_this_????,
	title = {This is my {Homeland}: {Stories} of the effects of nuclear industries by people of the {Serpent} {River} {First} {Nation} and the north shore of {Lake} {Huron}},
	author = {{Lorraine}}
}

@article{santoro_radiation_2000,
	title = {Radiation {Shielding} for {Fusion} {Reactors}},
	volume = {37},
	issn = {0022-3131},
	url = {http://dx.doi.org/10.1080/00223131.2000.10874838},
	doi = {10.1080/00223131.2000.10874838},
	abstract = {Radiation shielding requirements for fusion reactors present different problems than those for fission reactors and accelerators. Fusion devices, particularly tokamak reactors, are complicated by geometry constraints that complicate disposition of fully effective shielding. This paper reviews some of these shielding issues and suggested solutions for optimizing the machine and biological shielding. Radiation transport calculations are essential for predicting and confirming the nuclear performance of the reactor and, as such, must be an essential part of the reactor design process. Development and optimization of reactor components from the first wall and primary shielding to the penetrations and containment shielding must be carried out in a sensible progression. Initial results from one-dimensional transport calculations are used for scoping studies and are followed by detailed two- and three-dimensional analyses to effectively characterize the overall radiation environment. These detail model calculations are essential for accounting for the radiation leakage through ports and other penetrations in the bulk shield. Careful analysis of component activation and radiation damage is cardinal for defining remote handling requirements, in-situ replacement of components, and personnel access at specific locations inside the reactor containment vessel.},
	number = {sup1},
	urldate = {2016-11-27},
	journal = {Journal of Nuclear Science and Technology},
	author = {Santoro, R. T.},
	month = mar,
	year = {2000},
	keywords = {cross sections, dose, fusion reactor, nuclear heating, radiation damage, radiation transport, shielding},
	pages = {11--18},
	file = {Full Text PDF:files/122/Santoro - 2000 - Radiation Shielding for Fusion Reactors.pdf:application/pdf;Snapshot:files/123/00223131.2000.html:text/html}
}

@misc{_elliot_????,
	title = {Elliot {Lake} {Uranium} {Mines} {\textbar} {MiningWatch} {Canada}},
	url = {http://miningwatch.ca/blog/2005/9/13/elliot-lake-uranium-mines},
	urldate = {2016-10-22},
	file = {Elliot Lake Uranium Mines | MiningWatch Canada:files/57/elliot-lake-uranium-mines.html:text/html}
}

@article{shikama_behavior_1994,
	title = {Behavior of radiation-resistant optical fibers under irradiation in a fission reactor},
	volume = {212-1},
	issn = {00223115},
	doi = {10.1016/0022-3115(94)90097-3},
	abstract = {Two kinds of optical fibers were irradiated in a fission reactor, JMTR (Japan Materials Testing Reactor), up to a 1.55  1019 n/cm2 fast neutron fluence and a 3.3  109 Gy ionizing dose at 370 K. Optical transmission spectra were measured in the wavelength range of 450-1750 nm, in situ. Growth of strong optical absorption bands and a peak were observed in the range of wavelength shorter than 750 nm. In the meantime, the fibers showed good radiation-resistance in the range of wavelength larger than 750 nm. Some optical radiation from the fibers was observed. The main cause of the optical radiation is thought to be so-called Cherenkov radiation.},
	number = {pt A},
	journal = {Journal of Nuclear Materials},
	author = {Shikama, Tatsuo and Kakuta, Tsunemi and Narui, Minoru and Sagawa, Tsutomu and Shamoto, Naoki and Uramoto, Toshimasa and Sanada, Kazuo and Kayano, Hideo},
	year = {1994},
	keywords = {Fluorescence, Light absorption, Luminescence, Neutrons, Nuclear reactors, Optical fibers, Optical variables measurement, Radiation, Radiation effects, Reactor cores},
	pages = {421--425},
	file = {1-s2.0-0022311594900973-main.pdf:files/15/1-s2.0-0022311594900973-main.pdf:application/pdf}
}

@misc{_nuclear_2016,
	title = {Nuclear weapons and the {United} {States}},
	copyright = {Creative Commons Attribution-ShareAlike License},
	url = {https://en.wikipedia.org/w/index.php?title=Nuclear_weapons_and_the_United_States&oldid=742579710},
	abstract = {The United States was the first country to manufacture nuclear weapons, and is the only country to have used them in combat, with the separate bombings of Hiroshima and Nagasaki in World War II. Before and during the Cold War, it conducted over a thousand nuclear tests and tested many long-range nuclear weapons delivery systems.
Between 1940 and 1996, the U.S. government spent at least \$8.8 trillion in present-day terms on nuclear weapons, including platforms development (aircraft, rockets and facilities), command and control, maintenance, waste management and administrative costs. It is estimated that, since 1945, the United States produced more than 70,000 nuclear warheads, which is more than all other nuclear weapon states combined. The Soviet Union/Russia has produced approximately 55,000 nuclear warheads since 1949, France built 1110 warheads since 1960, the United Kingdom built 835 warheads since 1952, China built about 600 warheads since 1964, and other nuclear powers built fewer than 500 warheads all together since they developed their first nuclear weapons. Until November 1962, the vast majority of U.S. nuclear tests were aboveground. After the acceptance of the Partial Test Ban Treaty, all testing was relegated underground, in order to prevent the dispersion of nuclear fallout.
By February 2006 over \$1.2 billion in compensation had been paid to U.S. citizens exposed to nuclear hazards as a result of the U.S. nuclear weapons program, and by 1998 at least \$759 million had been paid to the Marshall Islanders in compensation for their exposure to U.S. nuclear testing.
In 2016, the United States maintained an arsenal of 4,500 warheads and facilities for their construction and design, though many of the Cold War facilities have since been deactivated and are sites for environmental remediation.},
	language = {en},
	urldate = {2016-10-22},
	journal = {Wikipedia},
	month = oct,
	year = {2016},
	note = {Page Version ID: 742579710},
	file = {Snapshot:files/59/index.html:text/html}
}

@article{jang_fiber-optic_2011,
	series = {Symposium on {Radiation} {Measurements} and {Applications} ({SORMA}) {XII} 2010},
	title = {Fiber-optic radiation sensor for detection of tritium},
	volume = {652},
	issn = {0168-9002},
	url = {http://www.sciencedirect.com/science/article/pii/S016890021002084X},
	doi = {10.1016/j.nima.2010.09.060},
	abstract = {The objective of this study is to develop the radiation sensor, which is composed of a scintillator, an optical fiber bundle and a light measuring device to detect the tritium in real-time. In this study, we have fabricated fiber-optic radiation sensors using inorganic scintillators and plastic optical fiber bundles. Each scintillator interacts with electron or beta ray and generates 455–550 nm wavelength of scintillation photons. An optical fiber bundle is usually made of plastic or glass, which is used to guide the light signal from a scintillating probe to light measuring device. For the purpose of selecting the best scintillator with a high efficiency, fiber-optic sensors manufactured using three kinds of inorganic scintillator such as Gd2O2S:Tb, Y3Al5O12:Ce and CsI:Tl, and they are tested with a metal hydride type of tritium source. In addition, the scintillation photons are measured as a function of distance between a fiber-optic sensor and source. Finally, we have measured the amounts of scintillation photon with different activities of tritium source and compared the measured results with those obtained using a surface activity monitor.},
	number = {1},
	urldate = {2016-09-26},
	journal = {Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment},
	author = {Jang, K. W. and Cho, D. H. and Yoo, W. J. and Seo, J. K. and Heo, J. Y. and Park, J. -Y. and Lee, B.},
	month = oct,
	year = {2011},
	keywords = {Beta ray, Fiber-optic sensor, Inorganic scintillator, Radiation detector, Tritium},
	pages = {928--931},
	file = {ScienceDirect Full Text PDF:files/144/Jang et al. - 2011 - Fiber-optic radiation sensor for detection of trit.pdf:application/pdf;ScienceDirect Snapshot:files/145/S016890021002084X.html:text/html}
}

@book{_dosimetry_2016,
	title = {Dosimetry},
	copyright = {Creative Commons Attribution-ShareAlike License},
	url = {https://en.wikipedia.org/w/index.php?title=Dosimetry&oldid=743446989},
	abstract = {Whilst Dosimetry in its original sense is the measurement of the absorbed dose delivered by ionizing radiation, the term is better known as a scientific sub-specialty in the fields of health physics and medical physics, where it is the calculation and assessment of the radiation dose received by the human body. Internal dosimetry due to the ingestion or inhalation of radioactive materials relies on a variety of physiological or imaging techniques. External dosimetry, due to irradiation from an external source is based on measurements with a dosimeter, or inferred from other radiological protection instruments. Dosimetry is used extensively for radiation protection and is routinely applied to occupational radiation workers, where irradiation is expected, but regulatory levels must not be exceeded. It is also used where radiation is unexpected, such as in the aftermath of the Three Mile Island, Chernobyl or Fukushima radiological release incidents, where the public irradiation is measured and calculated from a variety of indicators such as ambient measurements of radiation and radioactive contamination. Other significant areas are medical dosimetry, where the required treatment absorbed dose and any collateral absorbed dose is monitored, and in environmental dosimetry, such as radon monitoring in buildings.},
	language = {en},
	urldate = {2016-10-22},
	month = oct,
	year = {2016},
	note = {Page Version ID: 743446989},
	file = {Snapshot:files/132/index.html:text/html}
}

@misc{_research_????,
	title = {Research {Ethics}: {Historical} {Background} : {Essay} {Express} [2065]},
	shorttitle = {Research {Ethics}},
	url = {http://www.essayexpress.com/essay/research-ethics-historical-background/},
	abstract = {Essay Express! Examples of essays and research papers on many topics :: Research Ethics: Historical Background [2065]},
	urldate = {2016-10-22},
	journal = {Essay Express},
	file = {Snapshot:files/69/research-ethics-historical-background.html:text/html}
}

@article{brichard_radiation_2001,
	title = {Radiation effect in silica optical fiber exposed to intense mixed neutron-gamma radiation field},
	volume = {48},
	issn = {0018-9499},
	doi = {10.1109/23.983174},
	abstract = {We measured in situ the radiation-induced absorption of pure silica core fibers exposed to a fission nuclear reactor. We observed the growth of the 1.39-μm. OH vibration band in polymer coated fiber. Three mechanisms are responsible for this effect: recoil protons, hydrogen diffusion, and a probable compaction effect. Based on this experiment, a fiber-optic neutron monitor prototype is proposed},
	number = {6},
	journal = {IEEE Transactions on Nuclear Science},
	author = {Brichard, B. and Borgermans, P. and Fernandez, A. F. and Lammens, K. and Decreton, A.},
	month = dec,
	year = {2001},
	keywords = {1.39 micron, Absorption, Compaction, compaction effect, fiber-optic neutron monitor prototype, fibre optic sensors, fission nuclear reactor, Fission reactors, gamma-ray effects, Hydrogen, hydrogen diffusion, intense mixed neutron-gamma radiation field, Light absorption, neutron detection, neutron effects, Nuclear measurements, OH–centres, OH vibration band, Optical fibers, optical fiber sensor, polymer coated fiber, Polymer films, Protons, pure silica core fibers, radiation effect, Radiation effects, radiation-induced absorption, recoil protons, silica optical fiber, silicon compounds, SiO2:OH},
	pages = {2069--2073},
	file = {IEEE Xplore Abstract Record:files/35/983174.html:text/html;IEEE Xplore Full Text PDF:files/34/Brichard et al. - 2001 - Radiation effect in silica optical fiber exposed t.pdf:application/pdf}
}

@article{grattan_fiber_2000,
	title = {Fiber optic sensor technology: an overview},
	volume = {82},
	issn = {0924-4247},
	shorttitle = {Fiber optic sensor technology},
	url = {http://www.sciencedirect.com/science/article/pii/S0924424799003684},
	doi = {10.1016/S0924-4247(99)00368-4},
	abstract = {This work presents an overview of progress and developments in the field of fiber optic sensor technology, highlighting the major issues underpinning recent research and illustrating a number of important applications and key areas of effective fiber optic sensor development.},
	number = {1–3},
	urldate = {2016-09-26},
	journal = {Sensors and Actuators A: Physical},
	author = {Grattan, K. T. V. and Sun, T.},
	month = may,
	year = {2000},
	keywords = {Fiber optics, Measurement, Sensors},
	pages = {40--61},
	file = {ScienceDirect Full Text PDF:files/169/Grattan and Sun - 2000 - Fiber optic sensor technology an overview.pdf:application/pdf;ScienceDirect Snapshot:files/170/S0924424799003684.html:text/html}
}

@article{jang_development_2010,
	title = {Development of scintillation-fiber sensors for measurements of thermal neutrons in mixed neutron-gamma fields},
	volume = {56},
	issn = {ISSN 0374-4884},
	url = {http://inis.iaea.org/Search/search.aspx?orig_q=RN:44055988},
	language = {English},
	number = {6},
	urldate = {2016-09-26},
	journal = {Journal of the Korean Physical Society},
	author = {Jang, Kyoung Won and Yoo, Wook Jae and Park, Jang Yeon and Lee, Bong Soo},
	year = {2010},
	pages = {1777--1780},
	file = {0f3175332296298a56000000.pdf:files/165/0f3175332296298a56000000.pdf:application/pdf;Snapshot:files/166/search.html:text/html}
}

@article{shikama_behavior_1994-1,
	title = {Behavior of radiation-resistant optical fibers under irradiation in a fission reactor},
	volume = {212-1},
	issn = {00223115},
	doi = {10.1016/0022-3115(94)90097-3},
	abstract = {Two kinds of optical fibers were irradiated in a fission reactor, JMTR (Japan Materials Testing Reactor), up to a 1.55 1019 n/cm2 fast neutron fluence and a 3.3 109 Gy ionizing dose at 370 K. Optical transmission spectra were measured in the wavelength range of 450-1750 nm, in situ. Growth of strong optical absorption bands and a peak were observed in the range of wavelength shorter than 750 nm. In the meantime, the fibers showed good radiation-resistance in the range of wavelength larger than 750 nm. Some optical radiation from the fibers was observed. The main cause of the optical radiation is thought to be so-called Cherenkov radiation.},
	number = {pt A},
	journal = {Proceedings of the Sixth International Conference on Fusion Reactor Materials (ICFRM-6). Part A (of 4), September 27, 1993 - October 1, 1993},
	author = {Shikama, Tatsuo and Kakuta, Tsunemi and Narui, Minoru and Sagawa, Tsutomu and Shamoto, Naoki and Uramoto, Toshimasa and Sanada, Kazuo and Kayano, Hideo},
	year = {1994},
	keywords = {Fluorescence, Light absorption, Luminescence, Neutrons, Nuclear reactors, Optical fibers, Optical variables measurement, Radiation, Radiation effects, Reactor cores},
	pages = {421--425},
	file = {1-s2.0-0022311594900973-main.pdf:files/112/1-s2.0-0022311594900973-main.pdf:application/pdf}
}

@book{_introduction_????,
	title = {Introduction to {Nuclear} {Engineering}}
}

@article{santoro_radiation_2000-1,
	title = {Radiation {Shielding} for {Fusion} {Reactors}},
	volume = {37},
	issn = {0022-3131},
	url = {http://dx.doi.org/10.1080/00223131.2000.10874838},
	doi = {10.1080/00223131.2000.10874838},
	abstract = {Radiation shielding requirements for fusion reactors present different problems than those for fission reactors and accelerators. Fusion devices, particularly tokamak reactors, are complicated by geometry constraints that complicate disposition of fully effective shielding. This paper reviews some of these shielding issues and suggested solutions for optimizing the machine and biological shielding. Radiation transport calculations are essential for predicting and confirming the nuclear performance of the reactor and, as such, must be an essential part of the reactor design process. Development and optimization of reactor components from the first wall and primary shielding to the penetrations and containment shielding must be carried out in a sensible progression. Initial results from one-dimensional transport calculations are used for scoping studies and are followed by detailed two- and three-dimensional analyses to effectively characterize the overall radiation environment. These detail model calculations are essential for accounting for the radiation leakage through ports and other penetrations in the bulk shield. Careful analysis of component activation and radiation damage is cardinal for defining remote handling requirements, in-situ replacement of components, and personnel access at specific locations inside the reactor containment vessel.},
	number = {sup1},
	urldate = {2016-11-27},
	journal = {Journal of Nuclear Science and Technology},
	author = {Santoro, R. T.},
	month = mar,
	year = {2000},
	keywords = {cross sections, dose, fusion reactor, nuclear heating, radiation damage, radiation transport, shielding},
	pages = {11--18},
	file = {Full Text PDF:files/103/Santoro - 2000 - Radiation Shielding for Fusion Reactors.pdf:application/pdf;Snapshot:files/104/00223131.2000.html:text/html}
}

@book{_zotero_????,
	title = {Zotero {\textbackslash}textbar {Start}},
	url = {https://www.zotero.org/start_standalone},
	urldate = {2016-09-26},
	file = {Zotero | Start:files/158/start_standalone.html:text/html}
}

@book{cragg_canadian_1997,
	title = {Canadian {Issues} in {Environmental} {Ethics}},
	isbn = {978-1-55111-128-5},
	abstract = {Is it possible to design a forest policy that satisfies ethical and environmental concerns and is acceptable to business, labour and First Nations representatives? What is the best path through the tangle of ethical issues surrounding the collapse of the east coast fishery? What sort of obligations does a rich nation such as Canada have to satisfy the claims of global environmental justice? These are the sorts of issues in applied ethics that are tackled in this collection of essays, the vast majority of which have been written especially for this volume. It is the first Canadian collection of its kind. The book is divided in to sections detailing with such topics as the environment and the economy; ethical issues relating to non-human animals; issues of gender; and issues relating to native peoples. Most of the authors are philosophers, though specialists in geography, geology, and the social sciences are also among the contributors. Frequent reference is made to theoretical ethical concerns, but the focus throughout is on applied ethics, and a variety of case studies are included. (Examples include essays on animal rights and the case of native hunters; surface mining in Northern Ontario, the Quebec arctic; and fishing communities in the Maritimes.) Comparisons are frequently drawn to policies and ethical questions arising in other countries-most prominently the United States.},
	language = {en},
	publisher = {Broadview Press},
	author = {Cragg, Wesley and Greenbaum, Allan and Wellington, Alex},
	month = jun,
	year = {1997},
	note = {Google-Books-ID: w6ZVAgAAQBAJ},
	keywords = {Nature / Environmental Conservation \& Protection, Philosophy / Ethics \& Moral Philosophy}
}

@book{_this_????,
	title = {This is {My} {Homeland}: {Stories} of the effects of nuclear industries by people ({Review}) {\textbackslash}textbar {MiningWatch} {Canada}},
	url = {http://miningwatch.ca/blog/2006/12/2/my-homeland-stories-effects-nuclear-industries-people-review},
	urldate = {2016-10-22},
	file = {This is My Homeland\: Stories of the effects of nuclear industries by people (Review) | MiningWatch Canada:files/125/my-homeland-stories-effects-nuclear-industries-people-review.html:text/html}
}

@misc{_this_????-1,
	title = {This is {My} {Homeland}: {Stories} of the effects of nuclear industries by people ({Review}) {\textbar} {MiningWatch} {Canada}},
	url = {http://miningwatch.ca/blog/2006/12/2/my-homeland-stories-effects-nuclear-industries-people-review},
	urldate = {2016-10-22},
	file = {This is My Homeland\: Stories of the effects of nuclear industries by people (Review) | MiningWatch Canada:files/51/my-homeland-stories-effects-nuclear-industries-people-review.html:text/html}
}

@article{jang_development_2011,
	title = {Development and characterization of the integrated fiber-optic radiation sensor for the simultaneous detection of neutrons and gamma rays},
	volume = {69},
	issn = {0969-8043},
	url = {http://www.sciencedirect.com/science/article/pii/S096980431100011X},
	doi = {10.1016/j.apradiso.2011.01.009},
	abstract = {Sometimes, detection of thermal neutrons in the presence of gamma rays is required. This study developed and characterized an integrated fiber-optic radiation sensor for the simultaneous detection of thermal neutrons and gamma rays in a mixed radiation field. The performance of the integrated sensor was verified by measuring the distributions of thermal neutrons and gamma rays released from a nuclear fuel rod at the Kyoto University Critical Assembly. The experimental results show that the integrated sensor produced similar distribution patterns to those of thermal neutrons and gamma rays released from a fuel rod.},
	number = {4},
	urldate = {2016-09-26},
	journal = {Applied Radiation and Isotopes},
	author = {Jang, Kyoung Won and Lee, Bong Soo and Moon, Joo Hyun},
	month = apr,
	year = {2011},
	keywords = {Detection, Gamma rays, Integrated fiber-optic radiation sensor, Thermal neutrons},
	pages = {711--715},
	file = {ScienceDirect Full Text PDF:files/23/Jang et al. - 2011 - Development and characterization of the integrated.pdf:application/pdf;ScienceDirect Snapshot:files/24/S096980431100011X.html:text/html}
}

@article{stevenson_is_1989,
	title = {Is scientific research value‐neutral?},
	volume = {32},
	issn = {0020-174X},
	url = {http://www.tandfonline.com/doi/abs/10.1080/00201748908602188},
	doi = {10.1080/00201748908602188},
	abstract = {The conventional wisdom about the practice of science is that it is value‐free in the senses: (a) that science discovers facts, but there can be no scientific investigation of values; (b) that the only value recognized by the scientist qua scientist is that of knowing the truth; and (c) that the applications of scientific knowledge can, and should, be democratically decided by society as a whole. All three of these assumptions are open to question. Any human activity, including scientific research, involves a choice of how to spend time, effort, and resources; and given twentieth‐century realities about the funding and applications of research, such choices are becoming increasingly important in science.},
	number = {2},
	urldate = {2016-10-22},
	journal = {Inquiry},
	author = {Stevenson, Leslie},
	month = jan,
	year = {1989},
	pages = {213--222},
	file = {Snapshot:files/67/00201748908602188.html:text/html}
}

@article{kalcheva_activation_2005,
	title = {Activation of the {Concrete} in the {Bio} {Shield} of {ITER}},
	url = {https://www.researchgate.net/publication/27412538_Activation_of_the_Concrete_in_the_Bio_Shield_of_ITER},
	abstract = {Calculations of neutron spectra in different parts of the tokamak building of ITER are performed. A computational geometry model of the tokamak building is prepared using MCNP-4C. The model...},
	urldate = {2016-11-25},
	journal = {ResearchGate},
	author = {Kalcheva, Silva and Koonen, Edgar},
	month = jan,
	year = {2005},
	file = {Snapshot:files/191/27412538_Activation_of_the_Concrete_in_the_Bio_Shield_of_ITER.html:text/html}
}

@article{fernandez_temperature_2002,
	title = {Temperature monitoring of nuclear reactor cores with multiplexed fiber {Bragg} grating sensors},
	volume = {41},
	issn = {0091-3286},
	url = {http://dx.doi.org/10.1117/1.1475739},
	doi = {10.1117/1.1475739},
	abstract = {In-core temperature measurement is a critical issue for the safe operation of nuclear reactors. Classical thermocouples require shielded connections and are known to drift under high neutron fluence. As an alternative, we propose to take advantage of the multiplexing capabilities of fiber Bragg grating (FBG) temperature sensors. Our experiments show that sensitivity to radiation depends on both the radiation field and the grating characteristics. For some FBGs installed in an air-cooled graphite-moderated nuclear reactor the difference between the measurements and the readings of calibrated backup thermocouples was within the measurement uncertainty. In the worst case, the difference saturated after 30 h of reactor operation at about 5°C. To reach megagray per hour level gamma-dose rates and 1019 neutron/cm2 fluences, we irradiated multiplexed FBG sensors in a material testing nuclear reactor. At room temperature, FBG temperature sensors can survive in such radiation conditions, but at 90°C a severe degradation is observed. We evidence the possibility to use FBG sensing technology for in-core monitoring of nuclear reactors with specific care under well-specified conditions. © 2002 Society of Photo-Optical Instrumentation Engineers.},
	number = {6},
	urldate = {2016-09-26},
	journal = {Optical Engineering},
	author = {Fernandez, Alberto Fernandez and Gusarov, Andrei I. and Brichard, Benoı⁁t and Bodart, Serge and Lammens, Koen and Berghmans, Francis and Decre´ton, Marc and Me´gret, Patrice and Blondel, Michel and Delchambre, Alain},
	year = {2002},
	pages = {1246--1254},
	file = {Full Text PDF:files/154/Fernandez et al. - 2002 - Temperature monitoring of nuclear reactor cores wi.pdf:application/pdf}
}

@misc{_dosimetry_2016-1,
	title = {Dosimetry},
	copyright = {Creative Commons Attribution-ShareAlike License},
	url = {https://en.wikipedia.org/w/index.php?title=Dosimetry&oldid=743446989},
	abstract = {Whilst Dosimetry in its original sense is the measurement of the absorbed dose delivered by ionizing radiation, the term is better known as a scientific sub-specialty in the fields of health physics and medical physics, where it is the calculation and assessment of the radiation dose received by the human body.
Internal dosimetry due to the ingestion or inhalation of radioactive materials relies on a variety of physiological or imaging techniques. External dosimetry, due to irradiation from an external source is based on measurements with a dosimeter, or inferred from other radiological protection instruments.
Dosimetry is used extensively for radiation protection and is routinely applied to occupational radiation workers, where irradiation is expected, but regulatory levels must not be exceeded. It is also used where radiation is unexpected, such as in the aftermath of the Three Mile Island, Chernobyl or Fukushima radiological release incidents, where the public irradiation is measured and calculated from a variety of indicators such as ambient measurements of radiation and radioactive contamination.
Other significant areas are medical dosimetry, where the required treatment absorbed dose and any collateral absorbed dose is monitored, and in environmental dosimetry, such as radon monitoring in buildings.},
	language = {en},
	urldate = {2016-10-22},
	journal = {Wikipedia},
	month = oct,
	year = {2016},
	note = {Page Version ID: 743446989},
	file = {Snapshot:files/47/index.html:text/html}
}

@book{_elliot_????-1,
	title = {Elliot {Lake} {Uranium} {Mines} {\textbackslash}textbar {MiningWatch} {Canada}},
	url = {http://miningwatch.ca/blog/2005/9/13/elliot-lake-uranium-mines},
	urldate = {2016-10-22},
	file = {Elliot Lake Uranium Mines | MiningWatch Canada:files/110/elliot-lake-uranium-mines.html:text/html}
}

@book{_institutional_????,
	title = {Institutional {Repository} of the {Belgian} {Nuclear} {Research} {Centre} ({SCK}-{CEN}): {Activation} of the {Concrete} in the {Bio} {Shield} of {ITER}},
	url = {http://publications.sckcen.be/dspace/handle/10038/246},
	urldate = {2016-11-25},
	file = {Institutional Repository of the Belgian Nuclear Research Centre (SCK-CEN)\: Activation of the Concrete in the Bio Shield of ITER:files/181/246.html:text/html}
}

@article{gujrathi_attenuation_1972,
	title = {The attenuation of fast neutrons in shielding materials},
	volume = {100},
	issn = {0029-554X},
	url = {http://www.sciencedirect.com/science/article/pii/0029554X72908191},
	doi = {10.1016/0029-554X(72)90819-1},
	abstract = {The attenuation of a fast (≈ 2.6 MeV) neutron beam by various new, polymeric materials has been measured using an indirect method with a Ge(Li) gamma-ray spectrometer. In addition an attempt was made to estimate the effect of these materials on the thermal flux. Macroscopic removal cross sections for the elements involved were deduced and compared to values inferred from total microscopic cross sections.},
	number = {3},
	urldate = {2016-10-31},
	journal = {Nuclear Instruments and Methods},
	author = {Gujrathi, S. C. and D'Auria, J. M.},
	month = may,
	year = {1972},
	pages = {445--452},
	file = {ScienceDirect Snapshot:files/76/0029554X72908191.html:text/html}
}

@book{_tortured_2011,
	title = {The tortured future of {Elliot} {Lake} – by {Lloyd} {Tataryn} ({Saturday} {Night}, {June}, 1976)},
	url = {http://www.republicofmining.com/2011/03/28/the-tortured-future-of-elliot-lake-%e2%80%93-by-lloyd-tataryn-saturday-night-june-1976/},
	abstract = {This article was orginally published in Saturday Night (a Canadian general interest magazine that ceased publication in 2005) in the June, 1976 issue. “The conditions in Elliot Lake are not the bes…},
	urldate = {2016-10-22},
	month = mar,
	year = {2011},
	file = {Snapshot:files/179/the-tortured-future-of-elliot-lake-–-by-lloyd-tataryn-saturday-night-june-1976.html:text/html}
}

@article{gloge_weakly_1971,
	title = {Weakly {Guiding} {Fibers}},
	volume = {10},
	issn = {0003-6935, 1539-4522},
	url = {https://www.osapublishing.org/abstract.cfm?URI=ao-10-10-2252},
	doi = {10.1364/AO.10.002252},
	language = {en},
	number = {10},
	urldate = {2016-09-26},
	journal = {Applied Optics},
	author = {Gloge, D.},
	month = oct,
	year = {1971},
	pages = {2252},
	file = {ao-10-10-2252.pdf:files/39/ao-10-10-2252.pdf:application/pdf}
}

@misc{center_for_history_and_new_media_zotero_????,
	title = {Zotero {Quick} {Start} {Guide}},
	url = {http://zotero.org/support/quick_start_guide},
	author = {{Center for History and New Media}},
	annote = {Welcome to Zotero!View the Quick Start Guide to learn how to begin collecting, managing, citing, and sharing your research sources.Thanks for installing Zotero.}
}

@book{cragg_canadian_1997-1,
	title = {Canadian {Issues} in {Environmental} {Ethics}},
	isbn = {978-1-55111-128-5},
	abstract = {Is it possible to design a forest policy that satisfies ethical and environmental concerns and is acceptable to business, labour and First Nations representatives? What is the best path through the tangle of ethical issues surrounding the collapse of the east coast fishery? What sort of obligations does a rich nation such as Canada have to satisfy the claims of global environmental justice?   These are the sorts of issues in applied ethics that are tackled in this collection of essays, the vast majority of which have been written especially for this volume. It is the first Canadian collection of its kind.   The book is divided in to sections detailing with such topics as the environment and the economy; ethical issues relating to non-human animals; issues of gender; and issues relating to native peoples. Most of the authors are philosophers, though specialists in geography, geology, and the social sciences are also among the contributors.  Frequent reference is made to theoretical ethical concerns, but the focus throughout is on applied ethics, and a variety of case studies are included. (Examples include essays on animal rights and the case of native hunters; surface mining in Northern Ontario, the Quebec arctic; and fishing communities in the Maritimes.) Comparisons are frequently drawn to policies and ethical questions arising in other countries-most prominently the United States.},
	language = {en},
	publisher = {Broadview Press},
	author = {Cragg, Wesley and Greenbaum, Allan and Wellington, Alex},
	month = jun,
	year = {1997},
	note = {Google-Books-ID: w6ZVAgAAQBAJ},
	keywords = {Nature / Environmental Conservation \& Protection, Philosophy / Ethics \& Moral Philosophy}
}

@book{lorraine_this_2004,
	address = {Cutler, Ont},
	title = {This {Is} {My} {Homeland}: {Stories} of the {Effects} of {Nuclear} {Industries} by {People} of the {Serpent} {River} {First} {Nation} and the {North} {Shore} of {Lake} {H}},
	isbn = {978-0-9733055-0-0},
	shorttitle = {This {Is} {My} {Homeland}},
	language = {English},
	publisher = {Serpent River First Nation},
	author = {Lorraine, Rekmans},
	month = jan,
	year = {2004}
}

@article{sato_shielding_1996,
	title = {Shielding {Analysis} for {Toroidal} {Field} {Coils} {Around} {Exhaust} {Duct} in {Fusion} {Experimental} {Reactors}},
	volume = {30},
	url = {http://www.osti.gov/scitech/biblio/447337},
	language = {English},
	number = {3},
	urldate = {2016-11-25},
	journal = {Fusion Technology},
	author = {Sato, Satoshi and Takatsu, Hideyuki and Seki, Yasushi and Maki, Koichi},
	month = dec,
	year = {1996},
	keywords = {ducts, electric coils, exhaust systems, iter tokamak, Neutrons, numerical data, physics, plasma physics and fusion, radiation protection, shielding, simulation, toroidal field divertors},
	file = {Snapshot:files/92/447337.html:text/html}
}

@inproceedings{jensen_demonstration_1997,
	title = {Demonstration of long-term optical fiber thermometry in the in-core region of a nuclear reactor},
	volume = {3172},
	url = {http://dx.doi.org/10.1117/12.279753},
	doi = {10.1117/12.279753},
	abstract = {An experimental demonstration of fiber optic temperature sensing in the in-core region of Japan Materials Testing Reactor from 250 to 750 degrees C is described. Temperature data could be obtained for two full-power weeks with neutron fluxes of approximately 1014 n/cm2/s and gamma dose rates of approximately 5 X 103 Gy/s. The measurements were based on thermally generated IR light within the optical fiber itself. The fiber thus served as both signal generator and signal transmitter to the out-of-core region. The fibers utilized in the experiments where of high OH pure-silica-core type and showed good radiation resistance. In the IR region the transmission of the fibers was only weakly affected by the incident radiation. Radiation induced luminescence and Cerenkov radiation in the optical fibers were found to have small influence on the signal in the IR window. The high OH content of the fibers used in the present experiment precluded the use of the spectral regions at 945, 1245, and 1390 nm, due to the high intrinsic and radiation induced absorption at these wavelengths. The use of silica fibers limited the maximum temperature to {\textbackslash}textless 1000 degrees C. The present experiments show that optical sensors based on IR emission can be used to monitor temperature in the in-core region of nuclear reactors for extended periods of time.},
	urldate = {2016-09-26},
	author = {Jensen, Fredrik B. H. and Nakazawa, Masaharu and Kakuta, Tsunemi and Shikama, Tatsuo and Narui, Minoru and Sagawa, Tsutomu},
	year = {1997},
	pages = {467--477},
	file = {Full Text PDF:files/160/Jensen et al. - 1997 - Demonstration of long-term optical fiber thermomet.pdf:application/pdf}
}

@article{jang_fiber-optic_2011-1,
	series = {Symposium on {Radiation} {Measurements} and {Applications} ({SORMA}) {XII} 2010},
	title = {Fiber-optic radiation sensor for detection of tritium},
	volume = {652},
	issn = {0168-9002},
	url = {http://www.sciencedirect.com/science/article/pii/S016890021002084X},
	doi = {10.1016/j.nima.2010.09.060},
	abstract = {The objective of this study is to develop the radiation sensor, which is composed of a scintillator, an optical fiber bundle and a light measuring device to detect the tritium in real-time. In this study, we have fabricated fiber-optic radiation sensors using inorganic scintillators and plastic optical fiber bundles. Each scintillator interacts with electron or beta ray and generates 455–550 nm wavelength of scintillation photons. An optical fiber bundle is usually made of plastic or glass, which is used to guide the light signal from a scintillating probe to light measuring device. For the purpose of selecting the best scintillator with a high efficiency, fiber-optic sensors manufactured using three kinds of inorganic scintillator such as Gd2O2S:Tb, Y3Al5O12:Ce and CsI:Tl, and they are tested with a metal hydride type of tritium source. In addition, the scintillation photons are measured as a function of distance between a fiber-optic sensor and source. Finally, we have measured the amounts of scintillation photon with different activities of tritium source and compared the measured results with those obtained using a surface activity monitor.},
	number = {1},
	urldate = {2016-09-26},
	journal = {Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment},
	author = {Jang, K. W. and Cho, D. H. and Yoo, W. J. and Seo, J. K. and Heo, J. Y. and Park, J. -Y. and Lee, B.},
	month = oct,
	year = {2011},
	keywords = {Beta ray, Fiber-optic sensor, Inorganic scintillator, Radiation detector, Tritium},
	pages = {928--931},
	file = {ScienceDirect Full Text PDF:files/29/Jang et al. - 2011 - Fiber-optic radiation sensor for detection of trit.pdf:application/pdf;ScienceDirect Snapshot:files/30/S016890021002084X.html:text/html}
}

@book{_nuclear_????,
	title = {{NUCLEAR} {GENOCIDE} {IN} {CANADA}},
	url = {http://www.porthopehistory.com/nucleargenocide/nucleargenocide_index.htm},
	urldate = {2016-10-14},
	file = {NUCLEAR GENOCIDE IN CANADA:files/183/nucleargenocide_index.html:text/html}
}

@article{stevenson_is_1989-1,
	title = {Is scientific research value‐neutral?},
	volume = {32},
	issn = {0020-174X},
	url = {http://www.tandfonline.com/doi/abs/10.1080/00201748908602188},
	doi = {10.1080/00201748908602188},
	abstract = {The conventional wisdom about the practice of science is that it is value‐free in the senses: (a) that science discovers facts, but there can be no scientific investigation of values; (b) that the only value recognized by the scientist qua scientist is that of knowing the truth; and (c) that the applications of scientific knowledge can, and should, be democratically decided by society as a whole. All three of these assumptions are open to question. Any human activity, including scientific research, involves a choice of how to spend time, effort, and resources; and given twentieth‐century realities about the funding and applications of research, such choices are becoming increasingly important in science.},
	number = {2},
	urldate = {2016-10-22},
	journal = {Inquiry},
	author = {Stevenson, Leslie},
	month = jan,
	year = {1989},
	pages = {213--222},
	file = {Snapshot:files/130/00201748908602188.html:text/html}
}

@article{hayashi_advanced_2009,
	series = {Fusion {Reactor} {MaterialsProceedings} of the {Thirteenth} {International} {Conference} on {Fusion} {Reactor} {Materials}},
	title = {Advanced neutron shielding material using zirconium borohydride and zirconium hydride},
	volume = {386–388},
	issn = {0022-3115},
	url = {http://www.sciencedirect.com/science/article/pii/S0022311508008209},
	doi = {10.1016/j.jnucmat.2008.12.073},
	abstract = {Neutron transport calculations have been carried out to assess the capability of zirconium borohydride (Zr(BH4)4) and zirconium hydride (ZrH2) as advanced shield materials, because excellent shields can be used to protect outer structural materials from serious activation. The neutron shielding capability of Zr(BH4)4 is lower than ZrH2, even though the hydrogen density of Zr(BH4)4 is slightly higher than that of ZrH2. High-Z atoms are effective in neutron shielding as well as hydrogen atoms. The combination of steel and Zr(BH4)4 can improve the neutron shielding capability. The combinations of (Zr(BH4)4 + F82H) and (ZrH2 + F82H) can reduce the thickness of the shield by 6.5\% and 19\% compared to (water + F82H), respectively. The neutron flux for Zr(BH4)4 is drastically reduced in the range of neutron energy below 100 eV compared to other materials, due to the effect of boron, which can lead to a reduction of radwaste from fusion reactors.},
	urldate = {2016-10-31},
	journal = {Journal of Nuclear Materials},
	author = {Hayashi, T. and Tobita, K. and Nakamori, Y. and Orimo, S.},
	month = apr,
	year = {2009},
	pages = {119--121},
	file = {ScienceDirect Full Text PDF:files/149/Hayashi et al. - 2009 - Advanced neutron shielding material using zirconiu.pdf:application/pdf;ScienceDirect Snapshot:files/150/S0022311508008209.html:text/html}
}

@article{gujrathi_attenuation_1972-1,
	title = {The attenuation of fast neutrons in shielding materials},
	volume = {100},
	issn = {0029-554X},
	url = {http://www.sciencedirect.com/science/article/pii/0029554X72908191},
	doi = {10.1016/0029-554X(72)90819-1},
	abstract = {The attenuation of a fast (≈ 2.6 MeV) neutron beam by various new, polymeric materials has been measured using an indirect method with a Ge(Li) gamma-ray spectrometer. In addition an attempt was made to estimate the effect of these materials on the thermal flux. Macroscopic removal cross sections for the elements involved were deduced and compared to values inferred from total microscopic cross sections.},
	number = {3},
	urldate = {2016-10-31},
	journal = {Nuclear Instruments and Methods},
	author = {Gujrathi, S. C. and D'Auria, J. M.},
	month = may,
	year = {1972},
	pages = {445--452},
	file = {ScienceDirect Snapshot:files/134/0029554X72908191.html:text/html}
}

@article{bosch_improved_1992,
	title = {Improved formulas for fusion cross-sections and thermal reactivities},
	volume = {32},
	issn = {0029-5515},
	url = {http://stacks.iop.org/0029-5515/32/i=4/a=I07},
	doi = {10.1088/0029-5515/32/4/I07},
	abstract = {For interpreting fusion rate measurements in present fusion experiments and predicting the fusion performance of future devices or of d-t experiments in present devices, it is important to know the fusion cross-sections as precisely as possible. Usually, it is not measured data that are used, but parametrizations of the cross-section as a function of the ion energy and parametrizations of the Maxwellian reactivity as a function of the ion-temperature. Since the publication of the parametrizations now in use, new measurements have been made and evaluations of the measured data have been improved by applying R-matrix theory. The authors show that the old parametrizations no longer adequately represent the experimental data and present new parametrizations based on R-matrix calculations for fusion cross-sections and Maxwellian reactivities for the reactions D(d,n) 3 He, D(d,p)T, T(d,n) 4 He and 3 He(d,p) 4 He},
	language = {en},
	number = {4},
	urldate = {2016-11-25},
	journal = {Nucl. Fusion},
	author = {Bosch, H.-S. and Hale, G. M.},
	year = {1992},
	pages = {611},
	file = {IOP Full Text PDF:files/90/Bosch and Hale - 1992 - Improved formulas for fusion cross-sections and th.pdf:application/pdf}
}

@article{brichard_radiation_2001-1,
	title = {Radiation effect in silica optical fiber exposed to intense mixed neutron-gamma radiation field},
	volume = {48},
	issn = {0018-9499},
	doi = {10.1109/23.983174},
	abstract = {We measured in situ the radiation-induced absorption of pure silica core fibers exposed to a fission nuclear reactor. We observed the growth of the 1.39-μm. OH vibration band in polymer coated fiber. Three mechanisms are responsible for this effect: recoil protons, hydrogen diffusion, and a probable compaction effect. Based on this experiment, a fiber-optic neutron monitor prototype is proposed},
	number = {6},
	journal = {IEEE Transactions on Nuclear Science},
	author = {Brichard, B. and Borgermans, P. and Fernandez, A. F. and Lammens, K. and Decreton, A.},
	month = dec,
	year = {2001},
	keywords = {1.39 micron, Absorption, Compaction, compaction effect, fiber-optic neutron monitor prototype, fibre optic sensors, fission nuclear reactor, Fission reactors, gamma-ray effects, Hydrogen, hydrogen diffusion, intense mixed neutron-gamma radiation field, Light absorption, neutron detection, neutron effects, Nuclear measurements, OH–centres, OH vibration band, Optical fibers, optical fiber sensor, polymer coated fiber, Polymer films, Protons, pure silica core fibers, radiation effect, Radiation effects, radiation-induced absorption, recoil protons, silica optical fiber, silicon compounds, SiO2:OH},
	pages = {2069--2073},
	file = {IEEE Xplore Abstract Record:files/118/983174.html:text/html;IEEE Xplore Full Text PDF:files/119/Brichard et al. - 2001 - Radiation effect in silica optical fiber exposed t.pdf:application/pdf}
}

@book{sporea_optical_2012,
	title = {Optical fibers and optical fiber sensors used in radiation monitoring},
	url = {http://citeseerx.ist.psu.edu/viewdoc/download?doi=10.1.1.672.7192&rep=rep1&type=pdf},
	urldate = {2016-09-26},
	publisher = {Citeseer},
	author = {Sporea, Dan and Sporea, Adelina and McCarthy, Denis and Lewis, Elfed and O'Keeffe, Sinead},
	year = {2012},
	file = {Optical Fibers and Optical Fiber Sensors Used In Radiation Monitoring:files/156/download.pdf:application/pdf}
}

@book{john_introduction_2001,
	edition = {Third Edition},
	title = {Introduction to {Nuclear} {Engineering}},
	url = {https://www.scribd.com/doc/49342634/Introduction-to-Nuclear-Engineering-John-R-Lamarsh-and-Anthony-J-Baratta},
	urldate = {2016-11-27},
	publisher = {Prentice Hall},
	author = {John, R. Lamarsh and Anthony, J. Baratta},
	year = {2001},
	file = {Snapshot:files/189/Introduction-to-Nuclear-Engineering-John-R-Lamarsh-and-Anthony-J-Baratta.html:text/html}
}

@article{milora_revised_1978,
	title = {A {Revised} {Neutral} {Gas} {Shielding} {Model} for {Pellet}-{Plasma} {Interactions}},
	volume = {6},
	issn = {0093-3813},
	doi = {10.1109/TPS.1978.4317167},
	abstract = {A revised neutral molecule ablation model is derived to describe the evaporation of a solid hydrogen pellet in a tokamak plasma. The approach taken is based on the theory of Parks, Turnbull, and Foster who postulate that a cloud of molecular hydrogen surrounding the pellet shields the surface from incoming energetic electrons and, in so doing, regulates the evaporation rate. This treatment differs from the earlier model in that the hydrodynamic behavior of the molecular cloud is analyzed without invoking the assumption that the flow of material away from the surface is sonic everywhere. Numerical solutions of the fluid dynamic equations, which include the effects of strong electron heating locally in the gas, reveal that the flow of material away from the pellet is initially retarded relative to the solution of Parks et al., and then rapidly accelerated and rarified. This behavior is more pronounced for higher temperature plasmas and the net effect is that pellet life times might be prolonged slightly at the higher temperatures over those predicted by the approximate sonic flow model. A simple injection depth scaling law is derived and estimates of pellet fueling velocity requirements are made for several tokamaks.},
	number = {4},
	journal = {IEEE Transactions on Plasma Science},
	author = {Milora, S. L. and Foster, C. A.},
	month = dec,
	year = {1978},
	keywords = {Clouds, Electrons, Equations, Fluid dynamics, Hydrodynamics, Hydrogen, Plasma temperature, Solid modeling, Surface treatment, Tokamaks},
	pages = {578--592},
	file = {IEEE Xplore Abstract Record:files/185/4317167.html:text/html;IEEE Xplore Full Text PDF:files/186/Milora and Foster - 1978 - A Revised Neutral Gas Shielding Model for Pellet-P.pdf:application/pdf}
}

@book{_dosimetry_2016-2,
	title = {Dosimetry},
	copyright = {Creative Commons Attribution-ShareAlike License},
	url = {https://en.wikipedia.org/w/index.php?title=Dosimetry&oldid=743446989},
	abstract = {Whilst Dosimetry in its original sense is the measurement of the absorbed dose delivered by ionizing radiation, the term is better known as a scientific sub-specialty in the fields of health physics and medical physics, where it is the calculation and assessment of the radiation dose received by the human body. Internal dosimetry due to the ingestion or inhalation of radioactive materials relies on a variety of physiological or imaging techniques. External dosimetry, due to irradiation from an external source is based on measurements with a dosimeter, or inferred from other radiological protection instruments. Dosimetry is used extensively for radiation protection and is routinely applied to occupational radiation workers, where irradiation is expected, but regulatory levels must not be exceeded. It is also used where radiation is unexpected, such as in the aftermath of the Three Mile Island, Chernobyl or Fukushima radiological release incidents, where the public irradiation is measured and calculated from a variety of indicators such as ambient measurements of radiation and radioactive contamination. Other significant areas are medical dosimetry, where the required treatment absorbed dose and any collateral absorbed dose is monitored, and in environmental dosimetry, such as radon monitoring in buildings.},
	language = {en},
	urldate = {2016-10-22},
	month = oct,
	year = {2016},
	note = {Page Version ID: 743446989},
	file = {Snapshot:files/174/index.html:text/html}
}

@book{page.creator:none_uranium_????,
	title = {Uranium mines and mills waste},
	url = {http://nuclearsafety.gc.ca/eng/waste/uranium-mines-and-millswaste/index.cfm#Ontario},
	abstract = {English description / Description en anglais},
	language = {en},
	urldate = {2016-10-22},
	author = {{page.creator:none}},
	file = {Snapshot:files/152/index.html:text/html}
}

@book{_nuclear_????-1,
	title = {{NUCLEAR} {GENOCIDE} {IN} {CANADA} {Part} 1},
	url = {http://www.porthopehistory.com/nucleargenocide/nucleargenocide1.htm},
	urldate = {2016-10-22},
	file = {NUCLEAR GENOCIDE IN CANADA Part 1:files/172/nucleargenocide1.html:text/html}
}

@article{hayashi_advanced_2009-1,
	series = {Fusion {Reactor} {MaterialsProceedings} of the {Thirteenth} {International} {Conference} on {Fusion} {Reactor} {Materials}},
	title = {Advanced neutron shielding material using zirconium borohydride and zirconium hydride},
	volume = {386–388},
	issn = {0022-3115},
	url = {http://www.sciencedirect.com/science/article/pii/S0022311508008209},
	doi = {10.1016/j.jnucmat.2008.12.073},
	abstract = {Neutron transport calculations have been carried out to assess the capability of zirconium borohydride (Zr(BH4)4) and zirconium hydride (ZrH2) as advanced shield materials, because excellent shields can be used to protect outer structural materials from serious activation. The neutron shielding capability of Zr(BH4)4 is lower than ZrH2, even though the hydrogen density of Zr(BH4)4 is slightly higher than that of ZrH2. High-Z atoms are effective in neutron shielding as well as hydrogen atoms. The combination of steel and Zr(BH4)4 can improve the neutron shielding capability. The combinations of (Zr(BH4)4 + F82H) and (ZrH2 + F82H) can reduce the thickness of the shield by 6.5\% and 19\% compared to (water + F82H), respectively. The neutron flux for Zr(BH4)4 is drastically reduced in the range of neutron energy below 100 eV compared to other materials, due to the effect of boron, which can lead to a reduction of radwaste from fusion reactors.},
	urldate = {2016-10-31},
	journal = {Journal of Nuclear Materials},
	author = {Hayashi, T. and Tobita, K. and Nakamori, Y. and Orimo, S.},
	month = apr,
	year = {2009},
	pages = {119--121},
	file = {ScienceDirect Full Text PDF:files/72/Hayashi et al. - 2009 - Advanced neutron shielding material using zirconiu.pdf:application/pdf;ScienceDirect Snapshot:files/73/S0022311508008209.html:text/html}
}

@misc{page.creator:none_uranium_????-1,
	title = {Uranium mines and mills waste},
	url = {http://nuclearsafety.gc.ca/eng/waste/uranium-mines-and-millswaste/index.cfm#Ontario},
	abstract = {English description / Description en anglais},
	language = {en},
	urldate = {2016-10-22},
	author = {page.creator:none},
	file = {Snapshot:files/53/index.html:text/html}
}

@article{fernandez_temperature_2002-1,
	title = {Temperature monitoring of nuclear reactor cores with multiplexed fiber {Bragg} grating sensors},
	volume = {41},
	issn = {0091-3286},
	url = {http://dx.doi.org/10.1117/1.1475739},
	doi = {10.1117/1.1475739},
	abstract = {In-core temperature measurement is a critical issue for the safe operation of nuclear reactors. Classical thermocouples require shielded connections and are known to drift under high neutron fluence. As an alternative, we propose to take advantage of the multiplexing capabilities of fiber Bragg grating (FBG) temperature sensors. Our experiments show that sensitivity to radiation depends on both the radiation field and the grating characteristics. For some FBGs installed in an air-cooled graphite-moderated nuclear reactor the difference between the measurements and the readings of calibrated backup thermocouples was within the measurement uncertainty. In the worst case, the difference saturated after 30 h of reactor operation at about 5°C. To reach megagray per hour level gamma-dose rates and 1019 neutron/cm2 fluences, we irradiated multiplexed FBG sensors in a material testing nuclear reactor. At room temperature, FBG temperature sensors can survive in such radiation conditions, but at 90°C a severe degradation is observed. We evidence the possibility to use FBG sensing technology for in-core monitoring of nuclear reactors with specific care under well-specified conditions. © 2002 Society of Photo-Optical Instrumentation Engineers.},
	number = {6},
	urldate = {2016-09-26},
	journal = {Opt. Eng},
	author = {Fernandez, Alberto Fernandez and Gusarov, Andrei I. and Brichard, Benoı⁁t and Bodart, Serge and Lammens, Koen and Berghmans, Francis and Decre´ton, Marc and Me´gret, Patrice and Blondel, Michel and Delchambre, Alain},
	year = {2002},
	pages = {1246--1254},
	file = {Full Text PDF:files/37/Fernandez et al. - 2002 - Temperature monitoring of nuclear reactor cores wi.pdf:application/pdf}
}

@book{sporea_optical_2012-1,
	title = {Optical fibers and optical fiber sensors used in radiation monitoring},
	url = {http://citeseerx.ist.psu.edu/viewdoc/download?doi=10.1.1.672.7192&rep=rep1&type=pdf},
	urldate = {2016-09-26},
	publisher = {Citeseer},
	author = {Sporea, Dan and Sporea, Adelina and McCarthy, Denis and Lewis, Elfed and O'Keeffe, Sinead},
	year = {2012},
	file = {Optical Fibers and Optical Fiber Sensors Used In Radiation Monitoring:files/31/download.pdf:application/pdf}
}

@misc{_zotero_????-1,
	title = {Zotero {\textbar} {Start}},
	url = {https://www.zotero.org/start_standalone},
	urldate = {2016-09-26},
	file = {Zotero | Start:files/5/start_standalone.html:text/html}
}

@article{sato_shielding_1996-1,
	title = {Shielding {Analysis} for {Toroidal} {Field} {Coils} {Around} {Exhaust} {Duct} in {Fusion} {Experimental} {Reactors}},
	volume = {30},
	url = {http://www.osti.gov/scitech/biblio/447337},
	language = {English},
	number = {3},
	urldate = {2016-11-25},
	journal = {Fusion Technology},
	author = {Sato, Satoshi and Takatsu, Hideyuki and Seki, Yasushi and Maki, Koichi},
	month = dec,
	year = {1996},
	keywords = {ducts, electric coils, exhaust systems, iter tokamak, Neutrons, numerical data, physics, plasma physics and fusion, radiation protection, shielding, simulation, toroidal field divertors},
	file = {Snapshot:files/142/447337.html:text/html}
}

@inproceedings{jensen_demonstration_1997-1,
	title = {Demonstration of long-term optical fiber thermometry in the in-core region of a nuclear reactor},
	volume = {3172},
	url = {http://dx.doi.org/10.1117/12.279753},
	doi = {10.1117/12.279753},
	abstract = {An experimental demonstration of fiber optic temperature sensing in the in-core region of Japan Materials Testing Reactor from 250 to 750 degrees C is described. Temperature data could be obtained for two full-power weeks with neutron fluxes of approximately 1014 n/cm2/s and gamma dose rates of approximately 5 X 103 Gy/s. The measurements were based on thermally generated IR light within the optical fiber itself. The fiber thus served as both signal generator and signal transmitter to the out-of-core region. The fibers utilized in the experiments where of high OH pure-silica-core type and showed good radiation resistance. In the IR region the transmission of the fibers was only weakly affected by the incident radiation. Radiation induced luminescence and Cerenkov radiation in the optical fibers were found to have small influence on the signal in the IR window. The high OH content of the fibers used in the present experiment precluded the use of the spectral regions at 945, 1245, and 1390 nm, due to the high intrinsic and radiation induced absorption at these wavelengths. The use of silica fibers limited the maximum temperature to {\textless} 1000 degrees C. The present experiments show that optical sensors based on IR emission can be used to monitor temperature in the in-core region of nuclear reactors for extended periods of time.},
	urldate = {2016-09-26},
	author = {Jensen, Fredrik B. H. and Nakazawa, Masaharu and Kakuta, Tsunemi and Shikama, Tatsuo and Narui, Minoru and Sagawa, Tsutomu},
	year = {1997},
	pages = {467--477},
	file = {Full Text PDF:files/9/Jensen et al. - 1997 - Demonstration of long-term optical fiber thermomet.pdf:application/pdf}
}

@article{cheymol_high_2008,
	title = {High {Level} {Gamma} and {Neutron} {Irradiation} of {Silica} {Optical} {Fibers} in {CEA} {OSIRIS} {Nuclear} {Reactor}},
	volume = {55},
	issn = {0018-9499},
	doi = {10.1109/TNS.2008.924056},
	abstract = {In the final objective of elaborating an optical sensor of dimensional change in a nuclear testing reactor, we present extreme high level irradiation tests, up to 1.3 1020 nfast/cm2 and 16 GGy, conducted on high purity silica and hollow core photonic bandgap (PBG) fibers. These tests are performed in the OSIRIS reactor at CEA Saclay. We measure continuously radiation induced absorption (RIA), at 3 optical wavelengths: 980 nm, 1064 nm and 1310 nm. The evolution with the time of the spectral dependency over larger wavelength range is also reported. As well as reporting RIA up to higher dose than presented before, we demonstrate here the excellent superiority of hollow core PBG fibers over their conventional counterparts in term of radiation resistance up to over 1020nfast/cm2 and 10 GGy. We also report some optical time domain reflectometry (OTDR) measurements that probe the irradiated parts of the fibers and show a back scattering peak which appears, widens spatially then duplicates. We provide an interpretation based on the change of silica when it turns to metamict phase.},
	number = {4},
	journal = {IEEE Transactions on Nuclear Science},
	author = {Cheymol, G. and Long, H. and Villard, J. F. and Brichard, B.},
	month = aug,
	year = {2008},
	keywords = {backscatter, backscattering, CEA OSIRIS nuclear reactor, Fiber, gamma-ray effects, high level gamma irradiation, high purity silica, hollow core fibers, Inductors, Irradiation, neutron effects, Neutron irradiation, Neutrons, nuclear testing reactor, Optical fibers, Optical fiber sensors, Optical fiber testing, optical fibres, optical fibre testing, Optical scattering, optical sensor, optical sensors, optical time domain reflectometry, photonic band gap, photonic bandgap fibers, photonics fiber, pure silica, radiation induced absorption, radiation resistance, silica optical fibers, silicon compounds, SiO2, spectral dependency, Ultraviolet sources, wavelength 980 nm, wavelength 1064 nm, wavelength 1310 nm},
	pages = {2252--2258},
	file = {IEEE Xplore Abstract Record:files/176/4636911.html:text/html;IEEE Xplore Full Text PDF:files/177/Cheymol et al. - 2008 - High Level Gamma and Neutron Irradiation of Silica.pdf:application/pdf}
}

@book{_introduction_????-1,
	title = {Introduction to {Nuclear} {Engineering}}
}

@book{_research_????-1,
	title = {Research {Ethics}: {Historical} {Background} : {Essay} {Express} [2065]},
	shorttitle = {Research {Ethics}},
	url = {http://www.essayexpress.com/essay/research-ethics-historical-background/},
	abstract = {Essay Express! Examples of essays and research papers on many topics :: Research Ethics: Historical Background [2065]},
	urldate = {2016-10-22},
	file = {Snapshot:files/116/research-ethics-historical-background.html:text/html}
}

@article{noda_induced_2004,
	series = {Proceedings of the 11th {International} {Conference} on {Fusion} {Reactor} {Materials} ({ICFRM}-11)},
	title = {Induced activity of several candidate superconductor materials in a tokamak-type fusion reactor},
	volume = {329–333, Part B},
	issn = {0022-3115},
	url = {http://www.sciencedirect.com/science/article/pii/S0022311504003290},
	doi = {10.1016/j.jnucmat.2004.04.164},
	abstract = {The induced activity and compositional change of several superconducting materials such as Nb-based alloys, V-based alloys and MgB2 have been evaluated with a numerical calculation. We assume that the materials are irradiated for 10 MW a/m2 at the magnet of the inboard position of a tokamak-type fusion reactor with a neutron wall loading of 1 MW/m2. The materials are Nb3Sn, Nb3Al, NbTi, NbZr, V2Zr, V2(Zr,Hf), V3Ga, V3Si and MgB2. Most of the induced activity of V-based alloys and MgB2 after the shutdown of the reactor is controlled by the 60Co formed from Cu. After the irradiation, the dose rate decreases to a safe level of 10 μSv/h within 30 years. However, Nb-based alloys are predicted to emit gamma rays for tens of thousands years. The compositional changes and irradiation damage of V-based alloys and MgB2 are minimal.},
	urldate = {2016-11-25},
	journal = {Journal of Nuclear Materials},
	author = {Noda, T and Takeuchi, T and Fujita, M},
	month = aug,
	year = {2004},
	pages = {1590--1593},
	file = {ScienceDirect Full Text PDF:files/80/Noda et al. - 2004 - Induced activity of several candidate superconduct.pdf:application/pdf;ScienceDirect Snapshot:files/81/S0022311504003290.html:text/html}
}

@article{jang_development_2010-1,
	title = {Development of scintillation-fiber sensors for measurements of thermal neutrons in mixed neutron-gamma fields},
	volume = {56},
	issn = {ISSN 0374-4884},
	url = {http://inis.iaea.org/Search/search.aspx?orig_q=RN:44055988},
	language = {English},
	number = {6},
	urldate = {2016-09-26},
	journal = {Journal of the Korean Physical Society},
	author = {Jang, Kyoung Won and Yoo, Wook Jae and Park, Jang Yeon and Lee, Bong Soo},
	year = {2010},
	pages = {1777--1780},
	file = {0f3175332296298a56000000.pdf:files/14/0f3175332296298a56000000.pdf:application/pdf;Snapshot:files/13/search.html:text/html}
}

@book{chapman_effective_1955,
	address = {Oak Ridge, Tennessee},
	title = {Effective {Neutron} {Removal} {Cross} {Section} for {Shielding}},
	url = {http://web.ornl.gov/info/reports/1955/3445603498123.pdf},
	publisher = {Oak Ridge National Laboratory},
	author = {Chapman, J.T. and Storrs, C.L.},
	year = {1955}
}

@book{chapman_effective_1955-1,
	address = {Oak Ridge, Tennessee},
	title = {Effective {Neutron} {Removal} {Cross} {Section} for {Shielding}},
	url = {http://web.ornl.gov/info/reports/1955/3445603498123.pdf},
	publisher = {Oak Ridge National Laboratory},
	author = {Chapman, J.T. and Storrs, C.L.},
	year = {1955}
}

@book{_nuclear_2016-1,
	title = {Nuclear weapons and the {United} {States}},
	copyright = {Creative Commons Attribution-ShareAlike License},
	url = {https://en.wikipedia.org/w/index.php?title=Nuclear_weapons_and_the_United_States&oldid=742579710},
	abstract = {The United States was the first country to manufacture nuclear weapons, and is the only country to have used them in combat, with the separate bombings of Hiroshima and Nagasaki in World War II. Before and during the Cold War, it conducted over a thousand nuclear tests and tested many long-range nuclear weapons delivery systems. Between 1940 and 1996, the U.S. government spent at least \$8.8 trillion in present-day terms on nuclear weapons, including platforms development (aircraft, rockets and facilities), command and control, maintenance, waste management and administrative costs. It is estimated that, since 1945, the United States produced more than 70,000 nuclear warheads, which is more than all other nuclear weapon states combined. The Soviet Union/Russia has produced approximately 55,000 nuclear warheads since 1949, France built 1110 warheads since 1960, the United Kingdom built 835 warheads since 1952, China built about 600 warheads since 1964, and other nuclear powers built fewer than 500 warheads all together since they developed their first nuclear weapons. Until November 1962, the vast majority of U.S. nuclear tests were aboveground. After the acceptance of the Partial Test Ban Treaty, all testing was relegated underground, in order to prevent the dispersion of nuclear fallout. By February 2006 over \$1.2 billion in compensation had been paid to U.S. citizens exposed to nuclear hazards as a result of the U.S. nuclear weapons program, and by 1998 at least \$759 million had been paid to the Marshall Islanders in compensation for their exposure to U.S. nuclear testing. In 2016, the United States maintained an arsenal of 4,500 warheads and facilities for their construction and design, though many of the Cold War facilities have since been deactivated and are sites for environmental remediation.},
	language = {en},
	urldate = {2016-10-22},
	month = oct,
	year = {2016},
	note = {Page Version ID: 742579710},
	file = {Snapshot:files/114/index.html:text/html}
}

@book{lorraine_this_2004-1,
	address = {Cutler, Ont},
	title = {This {Is} {My} {Homeland}: {Stories} of the {Effects} of {Nuclear} {Industries} by {People} of the {Serpent} {River} {First} {Nation} and the {North} {Shore} of {Lake} {H}},
	isbn = {978-0-9733055-0-0},
	shorttitle = {This {Is} {My} {Homeland}},
	language = {English},
	publisher = {Serpent River First Nation},
	author = {Lorraine, Rekmans},
	month = jan,
	year = {2004}
}

@article{grattan_fiber_2000-1,
	title = {Fiber optic sensor technology: an overview},
	volume = {82},
	issn = {0924-4247},
	shorttitle = {Fiber optic sensor technology},
	url = {http://www.sciencedirect.com/science/article/pii/S0924424799003684},
	doi = {10.1016/S0924-4247(99)00368-4},
	abstract = {This work presents an overview of progress and developments in the field of fiber optic sensor technology, highlighting the major issues underpinning recent research and illustrating a number of important applications and key areas of effective fiber optic sensor development.},
	number = {1–3},
	urldate = {2016-09-26},
	journal = {Sensors and Actuators A: Physical},
	author = {Grattan, K. T. V. and Sun, T.},
	month = may,
	year = {2000},
	keywords = {Fiber optics, Measurement, Sensors},
	pages = {40--61},
	file = {ScienceDirect Full Text PDF:files/26/Grattan and Sun - 2000 - Fiber optic sensor technology an overview.pdf:application/pdf;ScienceDirect Snapshot:files/27/S0924424799003684.html:text/html}
}

@misc{_nuclear_????-2,
	title = {{NUCLEAR} {GENOCIDE} {IN} {CANADA} {Part} 1},
	url = {http://www.porthopehistory.com/nucleargenocide/nucleargenocide1.htm},
	urldate = {2016-10-22},
	file = {NUCLEAR GENOCIDE IN CANADA Part 1:files/49/nucleargenocide1.html:text/html}
}

@article{korkut_investigation_2010,
	title = {Investigation of fast neutron shielding characteristics depending on boron percentages of {MgB}2, {NaBH}4 and {KBH}4},
	volume = {286},
	issn = {0236-5731, 1588-2780},
	url = {http://link.springer.com.libaccess.lib.mcmaster.ca/article/10.1007/s10967-010-0619-0},
	doi = {10.1007/s10967-010-0619-0},
	abstract = {The macroscopic cross-section Σ and average neutron fluence in matter Φ are usable factors to comment neutron shielding property of samples. In this paper, we have used MgB2, NaBH4 and KBH4 samples including different percentages of boron. Neutron macroscopic cross-section measurements of them have been done by using a source of mono-energetic neutrons (Eeff = 4.5 MeV 241Am–Be). Average neutron fluence values and double differential fast neutron flux distributions of each samples calculated by using FLUKA Monte Carlo code. Also half value layers (HVLs) of samples are compared to paraffin which is one of the most neutron moderators. As a result, growing boron concentration can raise neutron shielding property of materials.},
	language = {en},
	number = {1},
	urldate = {2016-11-27},
	journal = {J Radioanal Nucl Chem},
	author = {Korkut, T. and Karabulut, A. and Budak, G. and Korkut, H.},
	month = oct,
	year = {2010},
	pages = {61--65},
	file = {Full Text PDF:files/193/Korkut et al. - 2010 - Investigation of fast neutron shielding characteri.pdf:application/pdf;Snapshot:files/194/s10967-010-0619-0.html:text/html}
}

@misc{_dosimetry_2016-3,
	title = {Dosimetry},
	copyright = {Creative Commons Attribution-ShareAlike License},
	url = {https://en.wikipedia.org/w/index.php?title=Dosimetry&oldid=743446989},
	abstract = {Whilst Dosimetry in its original sense is the measurement of the absorbed dose delivered by ionizing radiation, the term is better known as a scientific sub-specialty in the fields of health physics and medical physics, where it is the calculation and assessment of the radiation dose received by the human body.
Internal dosimetry due to the ingestion or inhalation of radioactive materials relies on a variety of physiological or imaging techniques. External dosimetry, due to irradiation from an external source is based on measurements with a dosimeter, or inferred from other radiological protection instruments.
Dosimetry is used extensively for radiation protection and is routinely applied to occupational radiation workers, where irradiation is expected, but regulatory levels must not be exceeded. It is also used where radiation is unexpected, such as in the aftermath of the Three Mile Island, Chernobyl or Fukushima radiological release incidents, where the public irradiation is measured and calculated from a variety of indicators such as ambient measurements of radiation and radioactive contamination.
Other significant areas are medical dosimetry, where the required treatment absorbed dose and any collateral absorbed dose is monitored, and in environmental dosimetry, such as radon monitoring in buildings.},
	language = {en},
	urldate = {2016-10-22},
	journal = {Wikipedia},
	month = oct,
	year = {2016},
	note = {Page Version ID: 743446989},
	file = {Snapshot:files/45/index.html:text/html}
}

@article{cheymol_high_2008-1,
	title = {High {Level} {Gamma} and {Neutron} {Irradiation} of {Silica} {Optical} {Fibers} in {CEA} {OSIRIS} {Nuclear} {Reactor}},
	volume = {55},
	issn = {0018-9499},
	doi = {10.1109/TNS.2008.924056},
	abstract = {In the final objective of elaborating an optical sensor of dimensional change in a nuclear testing reactor, we present extreme high level irradiation tests, up to 1.3 1020 nfast/cm2 and 16 GGy, conducted on high purity silica and hollow core photonic bandgap (PBG) fibers. These tests are performed in the OSIRIS reactor at CEA Saclay. We measure continuously radiation induced absorption (RIA), at 3 optical wavelengths: 980 nm, 1064 nm and 1310 nm. The evolution with the time of the spectral dependency over larger wavelength range is also reported. As well as reporting RIA up to higher dose than presented before, we demonstrate here the excellent superiority of hollow core PBG fibers over their conventional counterparts in term of radiation resistance up to over 1020nfast/cm2 and 10 GGy. We also report some optical time domain reflectometry (OTDR) measurements that probe the irradiated parts of the fibers and show a back scattering peak which appears, widens spatially then duplicates. We provide an interpretation based on the change of silica when it turns to metamict phase.},
	number = {4},
	journal = {IEEE Transactions on Nuclear Science},
	author = {Cheymol, G. and Long, H. and Villard, J. F. and Brichard, B.},
	month = aug,
	year = {2008},
	keywords = {backscatter, backscattering, CEA OSIRIS nuclear reactor, Fiber, gamma-ray effects, high level gamma irradiation, high purity silica, hollow core fibers, Inductors, Irradiation, neutron effects, Neutron irradiation, Neutrons, nuclear testing reactor, Optical fibers, Optical fiber sensors, Optical fiber testing, optical fibres, optical fibre testing, Optical scattering, optical sensor, optical sensors, optical time domain reflectometry, photonic band gap, photonic bandgap fibers, photonics fiber, pure silica, radiation induced absorption, radiation resistance, silica optical fibers, silicon compounds, SiO2, spectral dependency, Ultraviolet sources, wavelength 980 nm, wavelength 1064 nm, wavelength 1310 nm},
	pages = {2252--2258},
	file = {IEEE Xplore Abstract Record:files/18/4636911.html:text/html;IEEE Xplore Full Text PDF:files/17/Cheymol et al. - 2008 - High Level Gamma and Neutron Irradiation of Silica.pdf:application/pdf}
}

@misc{_tortured_2011-1,
	title = {The tortured future of {Elliot} {Lake} – by {Lloyd} {Tataryn} ({Saturday} {Night}, {June}, 1976)},
	url = {http://www.republicofmining.com/2011/03/28/the-tortured-future-of-elliot-lake-%e2%80%93-by-lloyd-tataryn-saturday-night-june-1976/},
	abstract = {This article was orginally published in Saturday Night (a Canadian general interest magazine that ceased publication in 2005) in the June, 1976 issue. “The conditions in Elliot Lake are not the bes…},
	urldate = {2016-10-22},
	journal = {Republic of Mining},
	month = mar,
	year = {2011},
	file = {Snapshot:files/55/the-tortured-future-of-elliot-lake-–-by-lloyd-tataryn-saturday-night-june-1976.html:text/html}
}

@article{kugel_measurements_1995-1,
	series = {Proceedings of the {Third} {International} {Symposium} on {Fusion} {Nuclear} {Technology}},
	title = {Measurements of tokamak fusion test reactor {D}-{T} radiation shielding efficiency},
	volume = {28},
	issn = {0920-3796},
	url = {http://www.sciencedirect.com/science/article/pii/0920379695900802},
	doi = {10.1016/0920-3796(95)90080-2},
	abstract = {Measurements of neutron and gamma dose-equivalents were performed in the test cell, at the outer test cell wall, in nearby work areas, and out to the nearest property lines at a distance of 180 m. Argon ionization chambers, moderated 3He proportional counters, and fission chamber detectors were used to obtain measurements of neutron and gamma dose-equivalents per D-T neutron during individual tokamak fusion test reactor (TFTR) discharges. These measured neutron and gamma D-T dose-equivalents per TFTR neutron characterize the effects of local variations in material density resulting from the complex asymmetric site geometry. The measured dose-equivalents per TFTR D-T neutron and the cumulative neutron production were used to determine that the planned annual TFTR neutron production of 1 × 1021 D-T neutrons is consistent with the design objective of limiting the total dose-equivalent at the property line, from all radiation sources and pathways, to less than 10 mrem per year.},
	urldate = {2016-11-25},
	journal = {Fusion Engineering and Design},
	author = {Kugel, H. W and Ascione, G and Elwood, S and Gilbert, J and Ku, L. -P and Levine, J and Rule, K and Azziz, N and Goldhagen, P and Hajnal, F and Shebell, P},
	month = mar,
	year = {1995},
	pages = {534--544},
	file = {ScienceDirect Snapshot:files/108/0920379695900802.html:text/html}
}

@article{noda_induced_2004-1,
	series = {Proceedings of the 11th {International} {Conference} on {Fusion} {Reactor} {Materials} ({ICFRM}-11)},
	title = {Induced activity of several candidate superconductor materials in a tokamak-type fusion reactor},
	volume = {329–333, Part B},
	issn = {0022-3115},
	url = {http://www.sciencedirect.com/science/article/pii/S0022311504003290},
	doi = {10.1016/j.jnucmat.2004.04.164},
	abstract = {The induced activity and compositional change of several superconducting materials such as Nb-based alloys, V-based alloys and MgB2 have been evaluated with a numerical calculation. We assume that the materials are irradiated for 10 MW a/m2 at the magnet of the inboard position of a tokamak-type fusion reactor with a neutron wall loading of 1 MW/m2. The materials are Nb3Sn, Nb3Al, NbTi, NbZr, V2Zr, V2(Zr,Hf), V3Ga, V3Si and MgB2. Most of the induced activity of V-based alloys and MgB2 after the shutdown of the reactor is controlled by the 60Co formed from Cu. After the irradiation, the dose rate decreases to a safe level of 10 μSv/h within 30 years. However, Nb-based alloys are predicted to emit gamma rays for tens of thousands years. The compositional changes and irradiation damage of V-based alloys and MgB2 are minimal.},
	urldate = {2016-11-25},
	journal = {Journal of Nuclear Materials},
	author = {Noda, T and Takeuchi, T and Fujita, M},
	month = aug,
	year = {2004},
	pages = {1590--1593},
	file = {ScienceDirect Full Text PDF:files/162/Noda et al. - 2004 - Induced activity of several candidate superconduct.pdf:application/pdf;ScienceDirect Snapshot:files/163/S0022311504003290.html:text/html}
}

@article{gloge_weakly_1971-1,
	title = {Weakly {Guiding} {Fibers}},
	volume = {10},
	issn = {0003-6935, 1539-4522},
	url = {https://www.osapublishing.org/abstract.cfm?URI=ao-10-10-2252},
	doi = {10.1364/AO.10.002252},
	language = {en},
	number = {10},
	urldate = {2016-09-26},
	journal = {Applied Optics},
	author = {Gloge, D.},
	month = oct,
	year = {1971},
	pages = {2252},
	file = {ao-10-10-2252.pdf:files/136/ao-10-10-2252.pdf:application/pdf}
}

@article{jang_development_2011-1,
	title = {Development and characterization of the integrated fiber-optic radiation sensor for the simultaneous detection of neutrons and gamma rays},
	volume = {69},
	issn = {0969-8043},
	url = {http://www.sciencedirect.com/science/article/pii/S096980431100011X},
	doi = {10.1016/j.apradiso.2011.01.009},
	abstract = {Sometimes, detection of thermal neutrons in the presence of gamma rays is required. This study developed and characterized an integrated fiber-optic radiation sensor for the simultaneous detection of thermal neutrons and gamma rays in a mixed radiation field. The performance of the integrated sensor was verified by measuring the distributions of thermal neutrons and gamma rays released from a nuclear fuel rod at the Kyoto University Critical Assembly. The experimental results show that the integrated sensor produced similar distribution patterns to those of thermal neutrons and gamma rays released from a fuel rod.},
	number = {4},
	urldate = {2016-09-26},
	journal = {Applied Radiation and Isotopes},
	author = {Jang, Kyoung Won and Lee, Bong Soo and Moon, Joo Hyun},
	month = apr,
	year = {2011},
	keywords = {Detection, Gamma rays, Integrated fiber-optic radiation sensor, Thermal neutrons},
	pages = {711--715},
	file = {ScienceDirect Full Text PDF:files/127/Jang et al. - 2011 - Development and characterization of the integrated.pdf:application/pdf;ScienceDirect Snapshot:files/128/S096980431100011X.html:text/html}
}

@misc{_institutional_????-1,
	title = {Institutional {Repository} of the {Belgian} {Nuclear} {Research} {Centre} ({SCK}-{CEN}): {Activation} of the {Concrete} in the {Bio} {Shield} of {ITER}},
	url = {http://publications.sckcen.be/dspace/handle/10038/246},
	urldate = {2016-11-25},
	file = {Institutional Repository of the Belgian Nuclear Research Centre (SCK-CEN)\: Activation of the Concrete in the Bio Shield of ITER:files/88/246.html:text/html}
}

@misc{_nuclear_????-3,
	title = {{NUCLEAR} {GENOCIDE} {IN} {CANADA}},
	url = {http://www.porthopehistory.com/nucleargenocide/nucleargenocide_index.htm},
	urldate = {2016-10-14},
	file = {NUCLEAR GENOCIDE IN CANADA:files/42/nucleargenocide_index.html:text/html}
}

@article{milora_revised_1978-1,
	title = {A {Revised} {Neutral} {Gas} {Shielding} {Model} for {Pellet}-{Plasma} {Interactions}},
	volume = {6},
	issn = {0093-3813},
	doi = {10.1109/TPS.1978.4317167},
	abstract = {A revised neutral molecule ablation model is derived to describe the evaporation of a solid hydrogen pellet in a tokamak plasma. The approach taken is based on the theory of Parks, Turnbull, and Foster who postulate that a cloud of molecular hydrogen surrounding the pellet shields the surface from incoming energetic electrons and, in so doing, regulates the evaporation rate. This treatment differs from the earlier model in that the hydrodynamic behavior of the molecular cloud is analyzed without invoking the assumption that the flow of material away from the surface is sonic everywhere. Numerical solutions of the fluid dynamic equations, which include the effects of strong electron heating locally in the gas, reveal that the flow of material away from the pellet is initially retarded relative to the solution of Parks et al., and then rapidly accelerated and rarified. This behavior is more pronounced for higher temperature plasmas and the net effect is that pellet life times might be prolonged slightly at the higher temperatures over those predicted by the approximate sonic flow model. A simple injection depth scaling law is derived and estimates of pellet fueling velocity requirements are made for several tokamaks.},
	number = {4},
	journal = {IEEE Transactions on Plasma Science},
	author = {Milora, S. L. and Foster, C. A.},
	month = dec,
	year = {1978},
	keywords = {Clouds, Electrons, Equations, Fluid dynamics, Hydrodynamics, Hydrogen, Plasma temperature, Solid modeling, Surface treatment, Tokamaks},
	pages = {578--592},
	file = {IEEE Xplore Abstract Record:files/84/4317167.html:text/html;IEEE Xplore Full Text PDF:files/83/Milora and Foster - 1978 - A Revised Neutral Gas Shielding Model for Pellet-P.pdf:application/pdf}
}

@book{turner_atoms_2007,
	edition = {3rd},
	title = {Atoms, {Radiation}, and {Radiation} {Protection}},
	shorttitle = {Wiley},
	url = {http://www.wiley.com/WileyCDA/WileyTitle/productCd-3527406069.html},
	urldate = {2016-11-27},
	publisher = {Wiley},
	author = {Turner, James},
	year = {2007},
	file = {Snapshot:files/196/productCd-3527406069.html:text/html}
}

@book{lorraine_this_????-1,
	title = {This is my {Homeland}: {Stories} of the effects of nuclear industries by people of the {Serpent} {River} {First} {Nation} and the north shore of {Lake} {Huron}},
	author = {Lorraine}
}

@book{center_for_history_and_new_media_zotero_????-1,
	title = {Zotero {Quick} {Start} {Guide}},
	url = {http://zotero.org/support/quick_start_guide},
	author = {{Center for History and New Media}},
	annote = {Welcome to Zotero!View the Quick Start Guide to learn how to begin collecting, managing, citing, and sharing your research sources.Thanks for installing Zotero.}
}

@book{john_introduction_2001-1,
	edition = {Third Edition},
	title = {Introduction to {Nuclear} {Engineering}},
	url = {https://www.scribd.com/doc/49342634/Introduction-to-Nuclear-Engineering-John-R-Lamarsh-and-Anthony-J-Baratta},
	urldate = {2016-11-27},
	publisher = {Prentice Hall},
	author = {John, R. Lamarsh and Anthony, J. Baratta},
	year = {2001},
	file = {Snapshot:files/98/Introduction-to-Nuclear-Engineering-John-R-Lamarsh-and-Anthony-J-Baratta.html:text/html}
}

@article{kalcheva_activation_2005-1,
	title = {Activation of the {Concrete} in the {Bio} {Shield} of {ITER}},
	url = {https://www.researchgate.net/publication/27412538_Activation_of_the_Concrete_in_the_Bio_Shield_of_ITER},
	abstract = {Calculations of neutron spectra in different parts of the tokamak building of ITER are performed. A computational geometry model of the tokamak building is prepared using MCNP-4C. The model...},
	urldate = {2016-11-25},
	journal = {ResearchGate},
	author = {Kalcheva, Silva and Koonen, Edgar},
	month = jan,
	year = {2005},
	file = {Snapshot:files/86/27412538_Activation_of_the_Concrete_in_the_Bio_Shield_of_ITER.html:text/html}
}

@article{bosch_improved_1992-1,
	title = {Improved formulas for fusion cross-sections and thermal reactivities},
	volume = {32},
	issn = {0029-5515},
	url = {http://stacks.iop.org/0029-5515/32/i=4/a=I07},
	doi = {10.1088/0029-5515/32/4/I07},
	abstract = {For interpreting fusion rate measurements in present fusion experiments and predicting the fusion performance of future devices or of d-t experiments in present devices, it is important to know the fusion cross-sections as precisely as possible. Usually, it is not measured data that are used, but parametrizations of the cross-section as a function of the ion energy and parametrizations of the Maxwellian reactivity as a function of the ion-temperature. Since the publication of the parametrizations now in use, new measurements have been made and evaluations of the measured data have been improved by applying R-matrix theory. The authors show that the old parametrizations no longer adequately represent the experimental data and present new parametrizations based on R-matrix calculations for fusion cross-sections and Maxwellian reactivities for the reactions D(d,n) 3 He, D(d,p)T, T(d,n) 4 He and 3 He(d,p) 4 He},
	language = {en},
	number = {4},
	urldate = {2016-11-25},
	journal = {Nuclear Fusion},
	author = {Bosch, H.-S. and Hale, G. M.},
	year = {1992},
	pages = {611},
	file = {IOP Full Text PDF:files/147/Bosch and Hale - 1992 - Improved formulas for fusion cross-sections and th.pdf:application/pdf}
}