The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents

Journal of Nuclear Materials

Volumn 448, Issue 1-3, 2014, Pages 512-519

  Terrani, Kurt A ^a   Wang, Dean ^a   Ott, Larry J ^a   Montgomery, Robert O ^b  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

^b PACIFIC NORTHWEST NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENTS; COOLANTS; FUELS; HYDRAULICS; LIGHT WATER REACTORS; NUCLEAR FUEL ELEMENTS; PRESSURIZED WATER REACTORS; THERMAL CONDUCTIVITY; TRANSIENTS;

FUEL TEMPERATURE; FUEL THERMAL CONDUCTIVITY; LARGE BREAK LOSS OF COOLANT ACCIDENTS; REACTOR SYSTEMS; STORED ENERGY; TEMPERATURE RESPONSE; THERMAL HYDRAULICS; TIME-SCALES;

LOSS OF COOLANT ACCIDENTS;

EID: 84899639790     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2013.09.051     Document Type: Article

References (36)

1. D. Olander Journal of Nuclear Materials 389 2009 1 22
2. S. Zinkle, and G. Was Acta Materialia 61 2013 735 758
3. N.E. Todreas, and M.S. Kazimi Nuclear Systems I: Thermal Hydraulic Fundamentals 1993 Taylor and Francis
4. C. Shuffler, J. Trant, J. Malen, and N. Todreas Nuclear Engineering and Design 239 2009 1442 1460
5. P. Ferroni, C. Handwerk, and N. Todreas Nuclear Engineering and Design 239 2009 1544 1559
6. Nuclear Fuel Safety Criteria Technical Review, NEA Report No. 7072, third ed., Nuclear Energy Agency, OECD, Paris 2012.
7. Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, LWR Edition, NUREG-0800, Section 4.2 Fuel System Design, Rev. 3, US Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, March 2007.
8. - 10 Code of Federal Regulation 50.46.
9. Draft Regulatory Guide DG-1263, US Nuclear Regulatory Commission Office of Nuclear Regulatory Research, 2012.
10. J. Alvis, W. Liu, R. Montgomery, Fuel Reliability Program: Proposed RIA Acceptance Criteria, Report No. 1021036, Electric Power Research Institute, Palo Alto, CA, 2010.
11. D.R. Olander Fundamental Aspects of Nuclear Reactor Fuel Elements, TID-26711-P1 1976 Technical Information Center Springfield, VA
12. P.G. Lucuta, H. Matzke, and I.J. Hastings Journal of Nuclear Materials 232 1996 166 180
13. B. Boyack, and G. Lellouche Nuclear Engineering and Design 119 1990 1 15
14. G.E. Wilson Nuclear Engineering and Design 119 1990 17 31
15. TRACE: The TRAC/RELAP Advanced Computational Engine, US Nuclear Regulatory Commission, 2012.
16. D. Staicu, 2.17 - Thermal Properties of Irradiated UO2 and MOX, in: Comprehensive Nuclear Materials, J.M.K. Editor-in-Chief: Rudy, Ed., ed Oxford, Elsevier, 2012, pp. 439-464.
17. S. Yagnik, Thermal conductivity recovery phenomenon in Irradiated UO2 and (U, Gd)O2, presented at the ANS Topical Meeting on LWR Fuel Performance, Park City, Utah, 2000.
18. M. Amaya, M. Hirai, H. Sakurai, K. Ito, M. Sasaki, and T. Nomata et al. Journal of Nuclear Materials 300 2002 57 64
19. C. Ronchi, M. Sheindlin, D. Staicu, and M. Kinoshita Journal of Nuclear Materials 327 2004 58 76
20. C. Walker, D. Staicu, M. Sheindlin, D. Papaioannou, W. Goll, and F. Sontheimer Journal of Nuclear Materials 350 2006 19 39
21. I. Cohen, B. Lustman, and J.D. Eichenberg Journal of Nuclear Materials 3 1961 331 353
22. P. Betten Transactions of the American Nuclear Society 50 1985 239 240
23. W. Wiesenack, M. Vankeerberghen, R. Thankappan, Assessment of UO2 conductivity degradation based on in-pile temperature data, HWR-469, lnstitutt for energiteknikk, OECD Halden Reactor Project, 1996.
24. Y. Rashid, R. Dunham, R. Montgomery, Fuel Analysis and Licensing Code: FALCON MOD01: Volume 1: Theoretical and Numerical Bases, EPRI 1011307, Electric Power Research Institute, 2004.
25. V.V. Rondinella, and T. Wiss Materials Today 13 2010 24 32
26. SCDAP team, SCDAP/RELAP5/MOD 3.2 Code Manual, Volume IV: MATPRO - A Library of Materials Properties for Light-Water-Reactor Accident Analysis, NUREG/CR-6150, vol. 4, October 1997.
27. M.M. El-Wakil Nuclear Heat Transport 1971 American Nuclear Society
28. Fuel Cladding Failure Criteria, EUR 19256 EN, European Nuclear Commission, 1999.
29. Fuel design data, Nuclear Engineering International, vol. 49, September, pp. 26-35, 2004.
30. J. Crank, P. Nicolson, A practical method for numerical evaluation of solutions of partial differential equations of the heat-conduction type, in: Mathematical Proceedings of the Cambridge Philosophical Society, 1947, pp. 50-67.
31. K.A. Terrani, J.E. Seifried, and D.R. Olander Journal of Nuclear Materials 392 2009 192 199
32. L.J. Ott, K.R. Robb, D. Wang, Preliminary assessment of ATFs on LWR during normal operation and under DB and BDB accident conditions, Journal of Nuclear Materials, 448 (2014) 520-533, http://dx.doi.org/10.1016/j.jnucmat.2013. 09.052.
33. W. Wulff Nuclear Engineering and Design 119 1990 33 65
34. D. Powers, and R. Meyer Cladding Swelling and Rupture Models for LOCA Analysis, NUREG-0630 1980 US Nuclear Regulatory Commission
35. R. Gauntt, D. Kalinich, J. Cardoni, J. Phillips, A. Goldmann, S. Pickering, et al., Fukushima Daiichi Accident Study (Status as of April 2012), SAND2012-6173, Sandia National Laboratorym, July 2012.
36. K.A. Terrani, S.J. Zinkle, and L.L. Snead Journal of Nuclear Materials 448 2014 420 435 http://dx.doi.org/10.1016/j.jnucmat.2013.06.041