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New measurement of the $^{242} \text{Pu}(n, \gamma)$ cross section at n_TOF-EAR1 for MOX fuels: Preliminary results in the RRR
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with 238U to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing to the long-term sustainability of nuclear energy. The use of MOX fuels in the...
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Lenguaje: | eng |
Publicado: |
2017
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Materias: | |
Acceso en línea: | https://dx.doi.org/10.1051/epjconf/201714611045 http://cds.cern.ch/record/2315304 |