An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B-VIII.0-NJOY results for criticality safety benchmarks and benchmarks on the reactivity temperature coefficient
Since the nuclear data forms a vital component in reactor physics computations, the nuclear community needs processing codes as tools for translating the Evaluated Nuclear Data Files (ENDF) to simulate nuclear-related problems such as an ACE format that is used for MCNP. Errors, inaccuracies or disc...
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| Principais autores: | , , , |
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| Format: | Artigo |
| Sprog: | Inglês |
| Udgivet: |
Elsevier
2021-08-01
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| Serier: | Nuclear Engineering and Technology |
| Fag: | |
| Online adgang: | http://www.sciencedirect.com/science/article/pii/S1738573321001029 |
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