Nuclear analysis of PIE data of irradiated BWR 8×8-2 and 8×8-4 UO2 fuel assemblies

Journal of Nuclear Science and Technology

Volumn 45, Issue 11, 2008, Pages 1193-1214

  Yamamoto, Toru ^a   Yamamoto, Munenari ^b  

^a JAPAN NUCLEAR ENERGY SAFETY ORGANIZATION   (Japan)

^b Global Nuclear Fuel Japan Co Ltd   (Japan)

Author keywords

Burnup; BWR 8 8 UO2 fuel assembly; Fission product; Irradiated sample; Lattice analysis; MVP BURN; Pellet average inventory; Pellet radial distribution; Pu; SRAC; U

Indexed keywords

ACTINIDES; ATOMS; BOILING WATER REACTORS; CESIUM; CODES (SYMBOLS); EUROPIUM; FISSION PRODUCTS; ISOTOPES; NEODYMIUM; NEUTRON DETECTORS; NUCLEAR FUEL REPROCESSING; PELLETIZING; PLUTONIUM; PROBABILITY DISTRIBUTIONS;

BURNUP; IRRADIATED SAMPLE; LATTICE ANALYSIS; MVP-BURN; PELLET AVERAGE INVENTORY; PELLET RADIAL DISTRIBUTION; PU; SRAC; U;

ASSEMBLY;

EID: 56149125466     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2008.9711908     Document Type: Article

References (25)

1. On fully loading MOXfuel in the Advanced Light Water Reactors, Nuclear Safety Commission of Japan, Jun. 28, 1999 (1999), [in Japanese].
2. K. Suyama, T. Iwasaki, N. Hirakawa, “Analysis of post irradiation experiments in PWR using new data libraries,” J. Nucl. Sci. Technol., 31[6], 596 (1994).
3. K. Okumura, T. Mori, M. Nakagawa et al., “Validation of a continuous-energy Monte Carlo burn-up code MVP-BURN and its application to analysis of post irradiation experiment,” J. Nucl. Sci. Technol., 37[2], 128 (2000).
4. B. D. Murphy, R. T. Primm III, “Prediction of spent MOX and LEU fuel composition and comparison with measurements,” Proc. Int. Conf. on the PHYSOR 2000, Pittsburgh, USA, May 7-12, 2000 (2000).
5. C. Chabert, A. Santamarina, P. Bioux, “Elaboration and experimental validation of the APOLLO2 depletion transport route for PWR Pu recycling, ” Proc. Int. Conf. on the PHYSOR 2000, Pittsburgh, USA, May 7-12, 2000 (2000).
6. D. Fujiwara, S. Kosaka, “Isotopic concentration and criticality analysis of BWR spent nuclear fuel using CASMO, ” Proc. Int. Conf on the PHYSOR 2002, Seoul, Korea, Oct. 2-10, 2002 (2002).
7. B. Roque, N. Thiollay, P. Marimbeau et al., “Experimental validation of the code system “DARWIN ” for spent fuel isotopic predictions in fuel cycle applications, ” Proc. Int. Conf. on the PHYSOR 2002, Seoul, Korea, Oct. 2-10, 2002 (2002).
8. K. Suyama, H. Mochizuki, T. Kiyosumi, “Revised burnup code system SWAT: description and validation using postirradiation examination data, ” Nucl. Technol., 138[2], 97 (2002).
9. A. Courcelle, A. Santamarina, S. Mengelle, “Improvement of isotopic ratios prediction through Takahama-3 chemical assay with the JEFF3.0 nuclear data library, ” Proc. Int. Conf. on the PHYSOR 2004, Chicago, USA, Apr. 25-29, 2004 (2004).
10. 2 PIE data analysis, ” Proc. Int. Conf on the PHYSOR 2004, Chicago, USA, Apr. 25-29, 2004 (2004).
11. Y. Ando, K. Yoshioka, I. Mitsuhashi et al., “Development and verification of Monte Carlo burnup calculation system, Proc. Int. Conf. on the ICNC2003, Tokai, Japan, Oct. 20-24, 2003 (2003).
12. 2 fuel assemblies, ” J. Nucl. Sci. Technol., 45[6], 547-566 (2007).
13. 2 fuel assemblies and evaluation, ” Proc. Int. Conf. on the PHYSOR 2000, Pittsburgh, Pennsylvania, USA, May 7-12, 2000 (2000).
14. 2 assemblies using lattice physics method, ” J. Nucl. Sci. Technol., 45[1], 1 (2008).
15. Y. Nakahara, K. Suyama, J. Inagawa et al., “Nuclide composition benchmark data set for verifying burnup codes on spent light water reactor fuel, ” Nucl. Technol., 137, 111 (2002).
16. Safety Experiments of High Burn-up Fuel (BWR High Burn-up Fuel, Comprehensive Evaluation), Nuclear Power Engineering Corporation, Mar., 2002 (2002), [in Japanese].
17. Application for Establishment Permit of Modification of Unit 2 of Fukushima Power Station 2, Tokyo Electric Power Company, Sept. 29, 1986 (1986), [in Japanese].
18. Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method), ASTM E321-96 (2005).
19. K. Okumura, K. Kaneko, K. Tsuchihashi, SRAC95: General Purpose Neutronics Code System, JAERI-Data/Code 96-015 (JAERI) (1996), [in Japanese].
20. T. Nakagawa, K. Shibata, S. Chiba et al., “Japanese evaluated nuclear data library version 3 revision-2, ” J. Nucl. Sci. Technol., 32, 1259 (1995).
21. K. Kanda, T. Yamamoto, H. Matuura et al., “MOX fuel core physics experiments and analysis—aiming for Plutonium effective use—, ” Nihon-Genshiryoku-Gakkai Shi (J. At. Energy Soc. Jpn., 40[11], 834 (1998), [in Japanese].
22. Y. Nakahara, K. Suyama, T. Suzaki, Technical Development on Burn-up Credit for Spent LWR Fuels, JAERI-Tech 2000071 (2000), [in Japanese].
23. 2 fuel using JENDL, JEF and ENDF/B, ” Nuclear Data News, 74, 39 (2003), [in Japanese].
24. K. Tasaka, J. Katakura, H. Ihara et al., JNDC Nuclear Data Library of Fission Products—Second Version—, JAERI-1320 (1990).
25. On 9x9 Fuel of Boiling Water Reactor, GLR-001, Global nuclear fuel-Japan (2003), [in Japanese].