Development of FRENDY nuclear data processing code; Generation capability of multi-group cross sections from ACE file

Yamamoto, Akio*; Endo, Tomohiro*; Tada, Kenichi

A generation capability of multi-group cross sections from point-wise cross sections in ACE files is being developed as a function of the nuclear data processing code FRENDY. This presentation describes features of this function and comparison of the processing results between this function and GROUPR module in NJOY.

Language	:	English
Journal	:	Transactions of the American Nuclear Society
Volume	:	122
Number	:	1
Pages	:	p.714 - 717
Publication Year/Month	:	2020/06
Meeting title	:	American Nuclear Society 2020 Annual Meeting
Held date	:	2020/06
Location (city)	:	Phoenix (online)
Location (country)	:	U.S.A.
Patent information	:
PDF	:
Paper URL	:	https://doi.org/10.13182/T122-32047
DOI for research data	:
Keywords	:	FRENDY; NJOY; Multi-group cross section; ACE
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:

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Registration No. : BB20191824
JAEA Abstracts No. : 48001226
Paper Submission No. : 23474

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