Analyses of boiling water reactor mixed-oxide critical experiments with CASMO-4/SIMULATE-3
Journal Article
·
· Nuclear Science and Engineering
OSTI ID:109981
- Toden Software, Inc., Tokyo (Japan)
- Tokyo Electric Power Co. (Japan)
Critical experiments that used high-concentration mixed-oxide (MOX) fuels in boiling water reactor lattice configurations and that were performed in the VENUS International Program are analyzed with CASMO-4 (C-4)/SIMULATE-3 (S-3). Both heterogeneous full-core transport calculations by C-4 and nodal diffusion calculations by S-3 with single-bundle CASMO-4 constants are performed, and the obtained results, such as eigenvalues and pin power distributions, are compared against the measured results. The agreement between the calculations and the measurements is quite satisfactory, and a good predictive capability of C-4 and S-3 for MOX fuels is verified.
- OSTI ID:
- 109981
- Journal Information:
- Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 1 Vol. 121; ISSN NSENAO; ISSN 0029-5639
- Country of Publication:
- United States
- Language:
- English
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