Nuclear data processing code FRENDY: A verification with HTTR criticality benchmark experiments

Nozomu Fujimoto; Kenichi Tada; Hai Quan Ho; Shimpei Hamamoto; Satoru Nagasumi; Etsuo Ishitsuka

doi:10.1016/j.anucene.2021.108270

Nuclear data processing code FRENDY: A verification with HTTR criticality benchmark experiments

Nozomu Fujimoto, Kenichi Tada, Hai Quan Ho, Shimpei Hamamoto, Satoru Nagasumi, Etsuo Ishitsuka

Nuclear Energy Systems

Research output: Contribution to journal › Article › peer-review

2 Citations (Scopus)

Abstract

Japan Atomic Energy Agency has developed a new nuclear data processing code, named FRENDY, to generate ACE-formatted files from various evaluated nuclear libraries. A code-to-experiment verification of FRENDY processing was carried out in this study with criticality benchmark assessments of the high temperature engineering test reactor. The ACE files of the JENDL-4.0 and ENDF/B-VII.1 was generated successfully by FRENDY. These ACE files have been used in MCNP6 transport for various benchmark problems of the high temperature engineering test reactor. As a result, the k_eff and reaction rate obtained by MCNP6 calculation presented a good agreement compared to the experimental data. The proper ACE files generation by FRENDY was confirmed for the HTTR criticality calculations.

Original language	English
Article number	108270
Journal	Annals of Nuclear Energy
Volume	158
DOIs	https://doi.org/10.1016/j.anucene.2021.108270
Publication status	Published - Aug 2021

All Science Journal Classification (ASJC) codes

Nuclear Energy and Engineering

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10.1016/j.anucene.2021.108270

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title = "Nuclear data processing code FRENDY: A verification with HTTR criticality benchmark experiments",

abstract = "Japan Atomic Energy Agency has developed a new nuclear data processing code, named FRENDY, to generate ACE-formatted files from various evaluated nuclear libraries. A code-to-experiment verification of FRENDY processing was carried out in this study with criticality benchmark assessments of the high temperature engineering test reactor. The ACE files of the JENDL-4.0 and ENDF/B-VII.1 was generated successfully by FRENDY. These ACE files have been used in MCNP6 transport for various benchmark problems of the high temperature engineering test reactor. As a result, the keff and reaction rate obtained by MCNP6 calculation presented a good agreement compared to the experimental data. The proper ACE files generation by FRENDY was confirmed for the HTTR criticality calculations.",

author = "Nozomu Fujimoto and Kenichi Tada and {Quan Ho}, Hai and Shimpei Hamamoto and Satoru Nagasumi and Etsuo Ishitsuka",

note = "Publisher Copyright: {\textcopyright} 2021 The Authors",

year = "2021",

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doi = "10.1016/j.anucene.2021.108270",

language = "English",

volume = "158",

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TY - JOUR

T1 - Nuclear data processing code FRENDY

T2 - A verification with HTTR criticality benchmark experiments

AU - Fujimoto, Nozomu

AU - Tada, Kenichi

AU - Quan Ho, Hai

AU - Hamamoto, Shimpei

AU - Nagasumi, Satoru

AU - Ishitsuka, Etsuo

PY - 2021/8

Y1 - 2021/8

N2 - Japan Atomic Energy Agency has developed a new nuclear data processing code, named FRENDY, to generate ACE-formatted files from various evaluated nuclear libraries. A code-to-experiment verification of FRENDY processing was carried out in this study with criticality benchmark assessments of the high temperature engineering test reactor. The ACE files of the JENDL-4.0 and ENDF/B-VII.1 was generated successfully by FRENDY. These ACE files have been used in MCNP6 transport for various benchmark problems of the high temperature engineering test reactor. As a result, the keff and reaction rate obtained by MCNP6 calculation presented a good agreement compared to the experimental data. The proper ACE files generation by FRENDY was confirmed for the HTTR criticality calculations.

AB - Japan Atomic Energy Agency has developed a new nuclear data processing code, named FRENDY, to generate ACE-formatted files from various evaluated nuclear libraries. A code-to-experiment verification of FRENDY processing was carried out in this study with criticality benchmark assessments of the high temperature engineering test reactor. The ACE files of the JENDL-4.0 and ENDF/B-VII.1 was generated successfully by FRENDY. These ACE files have been used in MCNP6 transport for various benchmark problems of the high temperature engineering test reactor. As a result, the keff and reaction rate obtained by MCNP6 calculation presented a good agreement compared to the experimental data. The proper ACE files generation by FRENDY was confirmed for the HTTR criticality calculations.

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Nuclear data processing code FRENDY: A verification with HTTR criticality benchmark experiments

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