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Continuous energy cross section library JAC08T1 based on JENDL/AC for MCNP calculation of irradiation field in JMTR

Takemoto, Noriyuki; Okumura, Keisuke; Katakura, Junichi; Nagao, Yoshiharu; Kawamura, Hiroshi

The continuous energy cross section library for the Monte Carlo transport code MCNP, JAC08T1, has been generated from the latest version of Japanese evaluated nuclear data library JENDL/AC released in March, 2008. The latest version of NJOY (NJOY99.259), the evaluated nuclear data processing system, has been employed to produce the library after necessary modifications in order to process JENDL/AC.

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