@book{ThermalFluids,
	place={New York},
	title={Fundamentals of thermal-fluid sciences},
	publisher={McGraw-Hill},
	author={C¸engel, Yunus A and Cimbala, John M and Turner, Robert H},
	year={2012}
}
@article{UZrSystem,
	title={Uranium-zirconium based alloys part I: reference points for thermophysical properties},
	author={Dias, Marcio Soares and Mattos, Joao Roberto L de}
}
@article{D2O,
	author = {N. Matsunaga and A. Nagashima},
	title = {Transport Properties of Liquid and Gaseous D2O over a Wide Range of Temperature and Pressure},
	journal = {Journal of Physical and Chemical Reference Data},
	volume = {12},
	number = {4},
	pages = {933-966},
	year = {1983},
	OMIT_doi = {10.1063/1.555694},
	
	OMIT_URL = { 
	https://doi.org/10.1063/1.555694
	
	},
	OMIT_eprint = { 
	https://doi.org/10.1063/1.555694
	
}
}
@techreport{Manzer,
	author = {Manzer, A},
	title = {CANDU Fuel Performance},
	institution = {Atomic Energy Canada Ltd.},
	year = {1996},
	address = {Mississauga, Ontario, Canada}
}
@article{song,
	title={CANDU Fuel Performance},
	author={Wenhui, Song and Manzer, A},
	journal={AECL, Shanghai Nuclear Design and Research Institute}
}
@Manual{CANDU-6,
	title = {CANDU 6 Technical Summary},
	organization = {Atomic Energy Canada Ltd.},
	year = {2005}
}
@article{Zirc4,
	title={Thermal Conductivity and Heat Capacity of Zircaloy-2, -4 and Unalloyed Zirconium},
	author={Masayuki MURABAYASHI and Shigenori TANAKA and Yoichi TAKAHASHI},
	journal={Journal of Nuclear Science and Technology},
	volume={12},
	number={10},
	pages={661-662},
	year={1975},
	OMIT_doi={10.3327/jnst.12.661}
}
@article{thermalconductivity,
	title = "Thermal conductivities of actinides (U, Pu, Np, Cm, Am) and uranium-alloys (U–Zr, U–Pu–Zr and U–Pu–TRU–Zr)",
	journal = "Journal of Nuclear Materials",
	volume = "445",
	number = "1",
	pages = "272 - 280",
	year = "2014",
	OMIT_issn = "0022-3115",
	OMIT_doi = "https://doi.org/10.1016/j.jnucmat.2013.11.018",
	OMIT_url = "http://www.sciencedirect.com/science/article/pii/S0022311513012476",
	author = "Yeon Soo Kim and Tae Won Cho and Dong-Seong Sohn"
}

@Manual{canteachBundle,
	author = {Page, R.D.},
	title = {Canadian Power Reactor Fuel},
	organization = {Atomic Energy Canada Ltd.},
}
@article{TwistedTape,
	title = "Heat transfer and friction factor characteristics in turbulent flow through a tube fitted with perforated twisted tape inserts",
	journal = "International Communications in Heat and Mass Transfer",
	volume = "46",
	number = "Supplement C",
	pages = "49 - 57",
	year = "2013",
	OMIT_issn = "0735-1933",
	OMIT_doi = "https://doi.org/10.1016/j.icheatmasstransfer.2013.05.012",
	OMIT_url = "http://www.sciencedirect.com/science/article/pii/S0735193313001085",
	author = "M.M.K. Bhuiya and M.S.U. Chowdhury and M. Saha and M.T. Islam",
	keywords = "Perforated twisted tape insert, Nusselt number, Friction factor, Thermal performance factor"
}
@unpublished{2Phase,
	author = {Luxat, J.C.},
	title = {TWO-PHASE FLOW:
	FLOW REGIMES, PRESSURE DROP, BOILING HEAT TRANSFER, AND
	CRITICAL HEAT FLUX},
	note = {McMaster Engineering Physics 4NE3 Lecture Notes}
}
@unpublished{Lightbridge,
	author = {Totemeier, A and Shaprio, N and Vaidyanathan, S},
	title = {Lightbridge Corporation's Advanced Metallic Fuel},
}
@techreport{SubcooledBoiling,
	title={Boiling heat transfer for high velocity flow of highly subcooled water},
	author={Lekakh, Boris and Kazimi, Mujid S and Meyer, John E},
	year={1999},
	institution={Dept. of Nuclear Engineering, Massachusetts Institute of Technology}
}
@book{canteachPellet1,
	author = {Harms, A},
	title = {An Introduction to the CANDU Nuclear Energy Conversion System},
	publisher = {McMaster University},
	year = {1972},
	note = {Retrieved from: https://canteach.candu.org/Content%20Library/19750107.pdf}
} 
@article{UO2thermal,
	title = {A recommendation for the thermal conductivity of UO2},
	journal = {Journal of Nuclear Materials},
	volume = {166},
	number = {3},
	pages = {223 - 226},
	year = {1989},
	OMIT_issn = {0022-3115},
	OMIT_doi = {https://doi.org/10.1016/0022-3115(89)90218-3},
	OMIT_url = {http://www.sciencedirect.com/science/article/pii/0022311589902183},
	author = {J.H. Harding and D.G. Martin}
}
@Article{Hofman1990,
	author="Hofman, Gerard L.
	and Pahl, R. G.
	and Lahm, C. E.
	and Porter, D. L.",
	title="Swelling behavior of U-Pu-Zr fuel",
	journal="Metallurgical Transactions A",
	year="1990",
	month="Feb",
	day="01",
	volume="21",
	number="2",
	pages="517--528",
	OMIT_abstract="Recent fast reactor driver fuel tests in the Experimental Breeder Reactor II (EBR-II) have demonstrated good performance of U-Pu-Zr fuel alloys to burnups >15 at. pct. Postirradiation examination of these tests has yielded a large amount of fuel-swelling data and metallographic information. These data show that prior to making contact with the cladding tube, metallic alloy fuel swells rapidly due to its high fission-enhanced creep rate and irradiation growth. Measurements of macroscopic fuel slug growth during the entire fuel pin lifetime can now be understood by properly taking into account the irradiation environment and microstructural changes for the various alloy compositions. It has been determined that fission rate, temperature, and plutonium concentrations influence the observed macroscopic swelling rate.",
	OMIT_issn="1543-1940",
	OMIT_doi="10.1007/BF02671924",
	OMIT_url="https://doi.org/10.1007/BF02671924"
}
@unpublished{1Phase,
	author = {Luxat, J.C.},
	title = {NUCLEAR HEAT TRANSPORT:
	SINGLE PHASE FLOW AND HEAT TRANSFER},
	note = {McMaster Engineering Physics 4NE3 Lecture Notes}
}
@article{annulus,
	title={GENERAL DEPENDENCES FOR HEAT TREATMENT
	AT TURBULENT FLUID FLOW
	IN AN ANNULUS},
	author={Petukhov, B.S. and Roizen, L.I.},
	journal={Izvestiya of the USSR Academy of Sciences. Energy and transport},
	number={1},
	pages={103},
	year={1967}
}