Fission yields data generation and benchmarks of decay heat estimation of a nuclear fuel
Fission yields data with the ENDF-6 format of 235U, 239Pu, and several actinides dependent on incident neutron energies have been generated using the GEF code. In addition, fission yields data libraries of ORIGEN-S, -ARP modules in the SCALE code, have been generated with the new data. The decay hea...
Main Authors: | , , , |
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Format: | Article |
Language: | English |
Published: |
EDP Sciences
2017-01-01
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Series: | EPJ Web of Conferences |
Online Access: | https://doi.org/10.1051/epjconf/201714604048 |