Lumped pseudo fission products during burnup step in MCNP5-ORIGEN coupling system

Depletion calculation and accurate inventory of fission products in a nuclear system are required for criticality, safety and spent fuel management. Actual trend is to use Monte Carlo methods. It is well known that the fission process produces a large number of nuclides, some of which have a signifi...

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Veröffentlicht in:	Progress in nuclear energy (New series) 2016-04, Vol.88 (C), p.277-284
Hauptverfasser:	Benkharfia, Hocine, Zidi, Tahar, Belgaid, Mohamed
Format:	Artikel
Sprache:	eng
Schlagworte:	Cross sections End of cycle Fission products Mathematical analysis MCNP5 MCNP6 Nuclear engineering Nuclear power generation Nuclear reactor components Nuclear reactors Nuclides ORIGEN UZrH1.6 fuel
Online-Zugang:	Volltext
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