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Measurement of the neutron capture cross-section of $^{235}$U at the n TOF facility
The first crucial ingredient of reactor and fuel cycle analysis is nuclear data. When designing or assessing the safety of a reactor system, nuclear data for a wide range of reactions and materials has to be known. Designers and physicists must address many variants of nuclear plants and undertake e...
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| Lenguaje: | eng |
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2020
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| Acceso en línea: | http://cds.cern.ch/record/2729120 |