Sensitivity and Uncertainty Quantification of Neutronic Integral Data Using ENDF/B-VII.1 and JENDL-4.0 Evaluations
Many integral neutronic parameters such as the effective multiplication factors (keff) are based on neutron reactions with matter through cross sections. However, these cross sections present uncertainties, of origin multiple, which reduce the safety margin of nuclear installations. In order to mini...
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| Main Authors: | , , , , , |
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| Format: | Book Chapter |
| Language: | English |
| Published: |
IntechOpen
2020
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| Subjects: | |
| Online Access: | https://www.intechopen.com/chapters/72953 |
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