Development of the burn-up chain data chainJ40 based on JENDL-4.0

Okumura, Keisuke ; Kojima, Kensuke; Okamoto, Tsutomu

A set of burn-up chain data for the isotope generation and depletion calculations by SRAC or MVP-BURN codes was produced by using recent nuclear data based on JENDL-4.0. Compared with old chain data, fission product yields, isomeric ratios, half-lives are updated, with adding long-lived fission products in the chain. The new chain data was validated by post-irradiation examination analyses with neutron cross section data from JENDL-4.0.

Language	:	Japanese
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Meeting title	:	日本原子力学会2012年春の年会
Held date	:	2012/03
Location (city)	:	福井
Location (country)	:	日本
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Keywords	:	no keyword
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Registration No. : BB20112802
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