Analysis of core physics experiment on BWR 10x10 MOX fuel assemblies

International Conference on the Physics of Reactors 2010, PHYSOR 2010

Volumn 4, Issue , 2010, Pages 3009-3020

  Yamamoto, Toru ^a   Ando, Yoshihira ^a   Hong, Leim Peng ^b  

^a JAPAN NUCLEAR ENERGY SAFETY ORGANIZATION   (Japan)

^b Tokaimura   (Japan)

Author keywords

10x10 MOX assembly; BWR; Core analysis; Core physics experiment; Full MOX core

Indexed keywords

BEAM PLASMA INTERACTIONS; CODES (SYMBOLS); CORE ANALYSIS; DIFFUSION; EXPERIMENTAL REACTORS; LIBRARIES; LIGHT WATER REACTORS; MONTE CARLO METHODS; TRANSPORT PROPERTIES;

CORE PHYSICS EXPERIMENT; DIFFUSION AND TRANSPORT; DIFFUSION CALCULATION; FULL-MOX CORE; MONTE CARLO CALCULATION; NUCLEAR DATA LIBRARY; OPERATING CONDITION; TRANSPORT CALCULATION;

BOILING WATER REACTORS;

EID: 79952428172     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (18)

1. T. Ihara et al., "Full MOX core design in ABWR," Proc. Int. Conf. GENES4/ANP2003, Kyoto, Japan, Sep. 15-19, 2003, Paper 1018 (2003).
2. T. Yamamoto et al., " FUBILA: core physics experimental program aimed at validation of core analysis method for high burn up BWR full MOX cores," Proc. Int. Conf. GLOBAL 2005, Tsukuba, Japan, Oct 9-13, 2005, Paper 092 (2005).
3. T. Yamamoto et al., "Experimental Results and Analysis of Core Physics Experiments, FUBILA, for High Burn-up BWR Full MOX Cores," Proc. Int. Conf. PHYSOR 2006, Vancouver, Canada, Sept. 10-14, 2006, (2006).
4. T. Yamamoto et al., "Analysis of Core Physics Experiments on MOX Assemblies Loaded with Gd2O3-UO2 and UO2 rods," Proc. Int. Conf. ICAPP2009, Tokyo, Japan, May 10-14, 2009, Paper 9290 (2009).
5. P. Braise et al., "Deterministic modeling of 100%MOX ABWR lattices with increasing void fraction: validation of the REL2005 code package on FUBILA Experimental Program, ibid, Paper 9209 (2009).
6. T. Yamamoto et al., "Analysis of Reactivity Measurements in Core Physics Experiments on Full-MOX BWR," J. Nucl. Sci. Technol., 46[6], 599 (2009).
7. T. Yamamoto et al. "Lattice Physics Analysis of Burnups and Isotope Inventories of U, Pu and Nd of Irradiated BWR 9x9-9 UO2 Fuel Assemblies," J. Nucl. Sci. Technol., 45[6], 547 (2008).
8. J. Mondot et al., "EPICURE: An Experimental Programme Devoted to the Validation of the Calculational Schemes for Plutonium recycling in PWRs," Proc. Int. Conf. PHYSOR 1990, Marseille, France, April 23-27, 1990 (1990).
9. S. Izutu et al., "Study on High Performance MOX fuel and Core Design in Full MOX ABWR (1) by GNF," Proc. Int. Conf. GENES/ANP2003, Sep. 15-19, 2003, Kyoto, Japan (2003).
10. K. Okumura et al., SRAC2006: A Comprehensive Neutronic Calculation Code System, JAERI-Data/Code 2007-004 (JAERI), (2007).
11. K. Shibata et al., "Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3," J. Nucl. Sci. Technol., 39[11], 1125 (2002).
12. K. Tsuchihashi et al., Revised SRAC code system, JAERI-1302 (1986).
13. T.B. Fowler et al., Nuclear Reactor Analysis Code: CITATION, ORNL-TM-2496 (1969).
14. R.E. Alcouffe, DANTSYS: A Diffusion Accelerated Neutral Particle Transport Code System, LA-12969-M (June 1995).
15. R.J.J. Stamm'ler and M.J. Abbate, Method of Steady-State Reactor Physics in Nuclear Design, Accademic Press, (1983).
16. Y. Nagaya et al., MVP/GMVP II: general purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods, JAERI-1348 (2005).
17. A. Courcelle, R.D. Mcknight, Nuclear Data for Improved LEU-LWR Reactivity Predictions, NEA/WPEC-22, OECD 2006(2006).
18. T. Yamamoto, "Analysis of core physics experiments of high moderation full MOX LWR," Proc. of the 2005 Symposium on Nuclear Data, JAEA-Conf, 2006-009 (2006).