Neutronic performance of uranium nitride composite fuels in a PWR

Nuclear Engineering and Design

Volumn 275, Issue , 2014, Pages 393-407

  Brown, Nicholas R ^a   Aronson, Arnold ^a   Todosow, Michael ^a   Brito, Ryan ^a,b   McClellan, Kenneth J ^c  

^a BROOKHAVEN NATIONAL LABORATORY   (United States)

^b Intern from Texas AandM Department of Nuclear Engineering   (United States)

^c LOS ALAMOS NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

LIGHT WATER REACTORS; LOADING; NITRIDES; NUCLEAR FUELS; POROSITY; PRESSURIZED WATER REACTORS; SILICON; THERMAL CONDUCTIVITY; URANIUM COMPOUNDS; ZIRCONIUM; ZIRCONIUM ALLOYS;

ADVANCED COMPOSITES; ENHANCED THERMAL CONDUCTIVITY; OPERATIONAL ASSESSMENT; OPERATIONAL PERFORMANCE; POTENTIAL BENEFITS; REACTIVITY COEFFICIENTS; SENSITIVITY PARAMETERS; THEORETICAL DENSITY;

FUELS;

EID: 84902688988     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2014.04.040     Document Type: Article

References (46)

1. Y. Arai, M. Morihira, and T. Ohmichi The effect of oxygen impurity on the characteristics of uranium and uranium-plutonium mixed nitride fuels J. Nucl. Mater. 202 1993 70 78 (Pubitemid 23683304)
2. A.A. Bauer, J.B. Brown, E.O. Fromm, and V.W. Storhok Mixed nitride fuel irradiation performance Proceedings of Fast Reactor Fuel Element Technology Conference New Orleans, April 1971
3. B. Becker, R. Dagan, and G. Lochnert Proof and implementation of the stochastic formula for ideal gas, energy dependent scattering kernel Ann. Nucl. Energy 36 2009 470 474
4. F. Boylan, N. Brichacek, F. Franceschini, S. Johnson, E. Lahoda, J. Mazzoccoli, J. Secker, and P. Xu Development of LWR Fuels with Enhanced Accident Tolerance Interim Technical Report, Westinghouse Electric Company Technical Report (RT-TR-13-22), October 2 2013
5. N.R. Brown, H. Ludewig, A. Aronson, G. Raitses, M. Todosow, and Neutronic evaluation of a PWR with fully-ceramic micro-encapsulated fuel. Part I. Lattice benchmarking, cycle length, and reactivity coefficients Ann. Nucl. Energy 2013 10.1016/j.anucene.2013.05.025
6. N.R. Brown, H. Ludewig, A. Aronson, G. Raitses, and M. Todosow Neutronic evaluation of a PWR with fully-ceramic micro-encapsulated fuel. Part II. Nodal core calculations and preliminary study of thermal hydraulic feedback Ann. Nucl. Energy 2013 10.1016/j.anucene.2013.05.027
7. K.H. Chaudri, W. Tian, Y. Su, H. Zhao, D. Zhu, G. Su, and S. Qiu Coupled analysis for new fuel design using UN and UC for SCWR" Prog. Nucl. Energy 63 2013 57 65
8. C. Degueldre, T. Arima, and Y.W. Lee Thermal conductivity of zirconia based inert matrix fuel: use and abuse of the formal models for testing new experimental data J. Nucl. Mater. 319 2003 6 14
9. C. Degueldre, P. Tissot, H. Lartigue, and M. Pouchon Specific heat capacity and Debye temperature of zirconia and its solid solution Thermochim. Acta 403 2003 267 273
10. T.J. Downar, Y. Xu, V. Seker, and N. Hudson PARCS v3.0 U.S. NRC Core Neutronics Simulator User Manual, University of Michigan Technical Report (UM-NERS-09-0001), May 29 2013
11. See also: T.J. Downar, Y. Xu, V. Seker, and N. Hudson PARCS v3.0 U.S. NRC Core Neutronics Simulator Theory Manual, University of Michigan Technical Report, January 16 2012
12. M.J. Driscoll, T.J. Downar, and E.E. Pilat The Linear Reactivity Model for Nuclear Fuel Management 1990 American Nuclear Society La Grange Park, Illinois
13. T.S. Ellis Advanced Design Concepts for PWR and BWR High-Performance Annular Fuel Assemblies (M.S. Thesis) 2006 Massachusetts Institute of Technology
14. B. Feng, A. Karahan, and M.S. Kazimi Steady-state fuel behavior modeling of nitride fuels in FRAPCON-EP J. Nucl. Mater. 427 2012 30 38
15. B. Feng, E. Shwageraus, B. Forget, and M.S. Kazimi Light water breeding with nitride fuel Prog. Nucl. Energy 53 2011 862 866
16. E. Fridman, J. Leppanen, and C. Wemple Comparison of Serpent and HELIOS-2 as Applied for the PWR Few-Group Cross-section Generation, M&C 2013 Sun Valley, Idaho, May 5-9 2013
17. A. Griffith Accident Tolerant Fuels, April 22 2013 U.S. Nuclear Regulatory Commission www.nrc.gov/reading-rm/doc-collections/.../griffith- slides-20130422.pdf (retrieved 12.08.13)
18. S.L. Hayes, J.K. Thomas, and K.L. Peddicord Material property correlations for uranium mononitride. I. Physical properties J. Nucl. Mater. 171 1990 262 270 (Pubitemid 20708877)
19. See also parts II = IV: S.L. Hayes, J.K. Thomas, and K.L. Peddicord Material property correlations for uranium mononitride. II. Mechanical properties J. Nucl. Mater. 171 1990 271 288 (Pubitemid 20708878)
20. S.L. Hayes, J.K. Thomas, and K.L. Peddicord Material property correlations for uranium mononitride. III. Transport properties J. Nucl. Mater. 171 1990 289 299 (Pubitemid 20708879)
21. S.L. Hayes, J.K. Thomas, and K.L. Peddicord Material property correlations for uranium mononitride. IV. Thermodynamic properties J. Nucl. Mater. 171 1990 300 318 (Pubitemid 20708880)
22. T. Kikuchi, T. Takahashi, and S. Nasu Porosity dependence of thermal conductivity of uranium mononitride J. Nucl. Mater. 45 1972 284 292
23. J. Leppänen Development of a New Monte Carlo Reactor Physics Code (Ph.D. Dissertation) 2007 Helsinki University of Technology
24. J.E. Matos, and J.L. Snelgrove Research reactor core conversion handbook; Volume 4: Fuels (Appendices I-K), International Atomic Energy Agency Technical Report (IAEA-TECDOC-643) 1992
25. 2 ceramics for use in LWR inert matrix fuel J. Nucl. Mater. 342 2004 48 62
26. 2-x/2 (x = 0, 0.084, and 0.179) single crystals J. Eur. Ceram. Soc. 24 2004 3081 3089 (Pubitemid 38531753)
27. L.R. Morss, N.M. Edelstein, and J. Fuger The Chemistry of the Actinide and Transactinide Elements 4th ed. 2011 Springer Dordrecht, Netherlands
28. H. Muta, K. Kurosaki, and M. Uno Thermal and mechanical properties of uranium nitride prepared by SPS technique J. Mater. Sci. 43 2008 6429 6434
29. K.L. Peddicord, M.E. Cunningham, and A. Tripathi Porosity correction to thermal conductivity based on analytical temperature solutions Trans. Am. Nucl. Soc. 28 1978 548 549
30. Oak Ridge National Laboratory SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design, Oak Ridge National Laboratory Technical Report (ORNL/TM-2005/39), June 2011
31. S. Raghavan, M.J. Mayo, H. Wang, R.B. Dinwiddie, and W.D. Porter The effect of grain size, porosity and yttria content on the thermal conductivity of nanocrystalline zirconia Scr. Mater. 39 1998 1119 1125 (Pubitemid 128417529)
32. G. Raitses, H. Ludewig, A. Aronson, N. Simos, and M. Todosow Initial Assessment of the Impact of Particle Fuels on PWR Operating and Safety Envelopes, Brookhaven National Laboratory Technical Report (BNL-FCRD-AFC-2011- 004), October 2011
33. C. Ronchi, J.P. Ottaviani, C. Degueldre, and R. Calabrese Thermophysical properties of inert matrix fuels for actinide transmutation J. Nucl. Mater. 320 2003 54 65
34. S.B. Ross, M.S. El-Genk, and R.B. Matthews Thermal Conductivity Correlation for Uranium Nitride Fuel Between 10 and 1923 K J. Nucl. Mater. 151 1988 313 317 (Pubitemid 18605768)
35. S.B. Ross, M.S. El-Genk, and R.B. Matthews Uranium nitride fuel swelling correlation J. Nucl. Mater. 170 1990 169 177 (Pubitemid 21659835)
36. R.S. Sen, M.A. Pope, A.M. Ougouag, K. Pasamehmetoglu, and F. Venneri Assessment of possible cycle lengths for fully-ceramic micro-encapsulated fuel-based light water reactor concepts PHYSOR 2012-Advances in Reactor Physics-Linking Research, Industry, and Education, Knoxville, TN, April 15-20 2012
37. R.L. Simmons, N.D. Jones, F.D. Popa, D.E. Mueller, and J.E. Pritchett Integral fuel burnable absorbers with ZrB2 in pressurized water reactors Nucl. Technol. 80 1988 343 348
38. S. Sugihara, and S. Imoto Hydrolysis of urnaium nitrides J. Nucl. Sci. Technol. 6 5 1969 237 242
39. S. Sunder, and N.H. Miller XPS and XRD studies of corrosion of uranium nitride by water J. Alloys Compd. 271-273 1998 568 572 (Pubitemid 128425026)
40. K.A. Terrani, L.L. Snead, and J.C. Gehin Microencapsulated fuel technology for commercial light water and advanced reactor application J. Nucl. Mater. 427 2012 209 224
41. Y.S. Touloukian, R.W. Powell, C.Y. Ho, and P.G. Klemens Thermophysical Properties of Matter - The TPRC Data Series. Volume 2. Thermal Conductivity - Nonmetallic Solids. Thermophysical and Electronic Properties Information Analysis Center Technical Report, Lafayette, IN 1971
42. S.C. Weaver, J.L. Scott, R.L. Senn, and B.H. Montgomery Effects of Irradiation on Uranium Nitride under Space-Reactor Conditions, Oak Ridge National Laboratory Technical Report (ORNL-4461) 1969
43. Westinghouse Electric Company AP1000 European Design Control Document, Pittsburgh, PA 2009
44. P. Xu, J. Yan, E. Lahoda, and S. Ray Uranium mononitride as a potential commercial LWR fuel Proceedings of ICAPP'12, Chicago, IL, 24-28 June 2012
45. Y. Xu, and T.J. Downar GENPMAXS-V5 Code for Generating the PARCS Cross-section Interface File PMAXS, University of Michigan Technical Report, December 2011
46. J. Zakova, and J. Wallenius Fuel residence time in BWRs with nitride fuels Ann. Nucl. Energy 47 2012 182 191