Analysis of burnup and isotopic compositions of BWR 9x9 UO2 fuel assemblies

International Conference on the Physics of Reactors 2012, PHYSOR 2012: Advances in Reactor Physics

Volumn 1, Issue , 2012, Pages 299-310

  Suzuki, M ^a   Yamamoto, T ^a   Ando, Y ^a   Nakajima, T ^a  

^a JAPAN NUCLEAR ENERGY SAFETY ORGANIZATION   (Japan)

Author keywords

9x9 fuel assembly; Burnup; Burnup analysis; BWR; Isotopic composition; MVP BURN

Indexed keywords

BURN UP; BWR; FUEL ASSEMBLY; ISOTOPIC COMPOSITION; MVP-BURN;

CESIUM; EUROPIUM; FISSION PRODUCTS; GADOLINIUM; ISOTOPES; LIBRARIES; NEODYMIUM;

BOILING WATER REACTORS;

EID: 84870346660     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (12)

1. 2 Fuel Assemblies", J. Nucl. Sci. and Technol., 45[6], p.547-566, (2008).
2. 2 fuel and nucleonics analysis [1] Total scope and preliminary nucleonics analysis," Proc. Annual Meeting of Atomic Energy Society of Japan, I42(p.449), Fukui City, Japan, March 28-30, 2011 (2011), [in Japanese].
3. 2 fuel and nucleonics analysis [2] Measurements of FP nuclides", Proc. Annual Meeting of the Atomic Energy Society of Japan, I43(p.450), Fukui City, Japan, March 28-30, 2011 (2011), [in Japanese].
4. Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method), ASTM E321-96 (Reapproved 2005).
5. Application for Establishment Permit of Modification of Unit 1 and 2 of Fukushima Daini Power Station, Tokyo Electric Power Company, May 26, 1994 (1994), [in Japanese].
6. Y. Hirano et al., "Irradiation characteristics of BWR high burnup 9x9 lead use assemblies", Proc. International Topical Meeting on Light Water Reactor Fuel Performance, Kyoto, Japan, Oct. 2-6, 2005 (2005).
7. Y. Nagaya, K. Okumura, T. Mori 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, Japan Atomic Energy Research Institute (JAERI), (2005).
8. 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. and Technol., 37[2], p.128-138, (2000).
9. K. Shibata, T. Kawano, T. Nakagawa et al., "Japanese Evaluated Nuclear Data Library Version 3 revision-3: JENDL-3.3", J. Nucl. Sci. and Technol., 39[11], p.1125-1136 (2002).
10. K. Shibata, O. Iwamoto, T. Nakagawa et al., "JENDL-4.0: A New Library for Nuclear Science and Engineering", J. Nucl. Sci. and Technol., 48[1], p.1-30 (2011).
11. K. Okumura, T. Kugo, K. Kaneko et al., SRAC2006: A Comprehensive Neutronics Calculation Code System, JAEA-Data/Code2007-004, Japan Atomic Energy Agency (JAEA), (2007).
12. K. Tasaka, J. Katakura, H. Ihara et al., JNDC Nuclear Data Library of Fission Products - Second Version-, JAERI-320, Japan Atomic Energy Research Institute (JAERI), (1990).