Neutronic analysis code for fuel assembly using a vectorized Monte Carlo method
Journal Article
·
· Nuclear Science and Engineering; (USA)
OSTI ID:6836038
- Hitachi Ltd., Ibaraki (Japan). Energy Research Lab.
A fuel assembly analysis code, VMONT, in which a multigroup neutron transport calculation is combined with a burnup calculation, has been developed for comprehensive design work use. The neutron transport calculation is performed with a vectorized Monte Carlo method that can realize speeds {gt}10 times faster than those of a scalar Monte Carlo method. The validity of the VMONT code is shown through test calculations against continuous energy Monte Carlo calculations and the proteus tight lattice experiment.
- OSTI ID:
- 6836038
- Journal Information:
- Nuclear Science and Engineering; (USA), Vol. 103:4; ISSN 0029-5639
- Country of Publication:
- United States
- Language:
- English
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