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Report No.

Investigation of the impact of difference between open nuclear data processing codes on neutron transport calculations, 3; Difference of nuclear data processing method

Tada, Kenichi   ; Ikehara, Tadashi; Ono, Michitaka*; Tojo, Masayuki*

JAEA develops a nuclear data processing code FRENDY. We can comparison and verification of conventional nuclear data processing code using FRENDY. In this presentation, we focus on the thermal scattering law data. We found some problems of NJOY to process the thermal scattering law data as follows, (1) The generation of input file is complex and we found some inputting error in the official ACE library, (2) The maximum energy of ACE file is not identical to the inputted maximum energy, (3) If user uses iwt=2 option in ACER module, MCNP6.1 cannot treat this generated ACE file appropriately and the calculation will not completed This presentation explains the overview of these problems.



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