Analysis of burnup and isotopic compositions of BWR 9 x 9 UO{sub 2} fuel assemblies
- Nuclear Energy System Safety Div., Japan Nuclear Energy Safety Organization, 4-1-28 Toranomon, Minato-ku, Tokyo 105-0001 (Japan)
In order to extend isotopic composition data focusing on fission product nuclides, measurements are progressing using facilities of JAEA for five samples taken from high burnup BWR 9 x 9 UO{sub 2} fuel assemblies. Neutronics analysis with an infinite assembly model was applied to the preliminary measurement data using a continuous-energy Monte Carlo burnup calculation code MVP-BURN with nuclear libraries based on JENDL-3.3 and JENDL-4.0. The burnups of the samples were determined to be 28.0, 39.3, 56.6, 68.1, and 64.0 GWd/t by the Nd-148 method. They were compared with those calculated using node-average irradiation histories of power and in-channel void fractions which were taken from the plant data. The comparison results showed that the deviations of the calculated burnups from the measurements were -4 to 3%. It was confirmed that adopting the nuclear data library based on JENDL-4.0 reduced the deviations of the calculated isotopic compositions from the measurements for {sup 238}Pu, {sup 144}Nd, {sup 145}Nd, {sup 146}Nd, {sup 148}Nd, {sup 134}Cs, {sup 154}Eu, {sup 152}Sm, {sup 154}Gd, and {sup 157}Gd. On the other hand, the effect of the revision in the nuclear. data library on the neutronics analysis was not significant for major U and Pu isotopes. (authors)
- Research Organization:
- American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
- OSTI ID:
- 22105590
- Resource Relation:
- Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 12 refs.
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BURNUP
BWR TYPE REACTORS
CESIUM 134
COMPARATIVE EVALUATIONS
EUROPIUM 154
FISSION PRODUCTS
FUEL ASSEMBLIES
GADOLINIUM 154
GADOLINIUM 157
ISOTOPE RATIO
MONTE CARLO METHOD
NEODYMIUM 144
NEODYMIUM 145
NEODYMIUM 146
NEODYMIUM 148
NUCLEAR DATA COLLECTIONS
PLUTONIUM 238
SAMARIUM 152
URANIUM DIOXIDE