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Tada, Kenichi; Yamamoto, Akio*; Kunieda, Satoshi; Konno, Chikara; Kondo, Ryoichi; Endo, Tomohiro*; Chiba, Go*; Ono, Michitaka*; Tojo, Masayuki*
Journal of Nuclear Science and Technology, 10 Pages, 2023/00
Nuclear data processing code is important to connect evaluated nuclear data libraries and radiation transport codes. The nuclear data processing code FRENDY version 1 was released in 2019 to generate ACE formatted cross section files with simple input data. After we released FRENDY version 1, many functions were developed, e.g., neutron multi-group cross section generation, explicit consideration of the resonance interference effect among different nuclides in a material, consideration of the resonance upscattering, ACE file perturbation, and modification of ENDF-6 formatted file. FRENDY version 2 was released including these new functions. It generates GENDF and MATXS formatted neutron multi-group cross section files from an ACE formatted cross section file or an evaluated nuclear data file. This paper explains the features of the new functions implemented in FRENDY version 2 and the verification of the neutron multigroup cross section generation function of this code.
Tada, Kenichi; Yamamoto, Akio*; Endo, Tomohiro*; Chiba, Go*; Ono, Michitaka*; Tojo, Masayuki*
Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022) (Internet), 10 Pages, 2022/05
Nuclear data processing is an important interface between an evaluated nuclear data library and nuclear transport calculation codes. JAEA has developed a new nuclear data processing code FRENDY from 2013. FRENDY version 1 generates ACE files which are used for the continuous-energy Monte Carlo codes including PHITS, Serpent, and MCNP; it was released as an open-source software under the 2-clause BSD license in 2019. After FRENDY version 1 was released, many functions are developed: the multi-group neutron cross-section library generation, the statistical uncertainty quantification for the probability tables for unresolved resonance cross-section, the perturbation of the ACE file, and the modification of the ENDF-6 formatted nuclear data file, etc. We released FRENDY version 2 including these functions. This presentation explains the overview of FRENDY and features of the new functions implemented in FRENDY version 2.
Ono, Michitaka*; Tojo, Masayuki*; Tada, Kenichi; Yamamoto, Akio*
Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022) (Internet), 9 Pages, 2022/05
In this paper, nuclear calculations were performed using the ACE files and the multigroup libraries created by both FRENDY and NJOY, and the impacts on the neutronics characteristics due to nuclear data processing were investigated using those libraries. MCNP was used to compare the ACE files by calculating many benchmark problems including ICSBEP and it was confirmed that the k-eff values are generally agreed with each other within the range of statistical errors. The multigroup cross sections are verified by the BWR design codes LANCR/AETNA through calculation of a commercial-grade BWR5 equilibrium core loaded with 9
9 fuels. These results indicate that fuel assembly and core characteristics are consistent with each other. From the above investigations, it was confirmed that FRENDY can provide comparable continuous/multi-group neutron cross sections with NJOY.
Isono, Takaaki; Nunoya, Yoshihiko; Ando, Toshinari*; Okuno, Kiyoshi; Ono, Michitaka*; Ozaki, Akira*; Koizumi, Tsutomu*; Otani, Nozomu*; Hasegawa, Takayo*
IEEE Transactions on Applied Superconductivity, 13(2), p.1512 - 1515, 2003/06
Times Cited Count：21 Percentile：67.87(Engineering, Electrical & Electronic)Japan Atomic Energy Research Institute has started development work on a large current conductor using high Tc superconductor (HTS) aiming at a fusion power reactor after the International Thermonuclear Experimental Reactor (ITER). HTS has a capability to produce a magnetic field of higher than 16 T, which is required in such a fusion power reactor. A trial fabrication of a 10-kA 12-T conductor was started using round Ag-alloy sheathed Bi-2212 strands, which has best performance at 4.2K, 16T at present. The conductor has about 34-mm diameter, and is composed of 729 HTS strands. Operating temperature is designed at not only 4 K but also 20K. The conductor sample is indirectly cooled and is solder-coated on the surface to use specific heat of the lead as much as possible, which at 20 K is almost comparable with specific heat of SHe at 4.5K, 0.6MPa. From the tests of the conductor, the fabrication of large HTS conductor and 10kA operation at 12 T and about 12.5 K were successfully performed and the possibility of HTS to use fusion application was demonstrated.
Hamajima, Takataro*; Hanai, Satoshi*; Wachi, Yoshihiro*; Shimada, Mamoru*; Ono, Michitaka*; Martovetsky, N.*; Zbasnik, J.*; Moller, J.*; Takahashi, Yoshikazu; Matsui, Kunihiro; et al.
IEEE Transactions on Applied Superconductivity, 10(1), p.812 - 815, 2000/03
Times Cited Count：10 Percentile：53.66(Engineering, Electrical & Electronic)no abstracts in English
Hamajima, Takataro*; Shimada, Mamoru*; Ono, Michitaka*; Takigami, Hiroyuki*; Hanai, Satoshi*; Wachi, Yoshihiro*; Takahashi, Yoshikazu; Matsui, Kunihiro; Ito, Toshinobu*; Isono, Takaaki; et al.
Teion Kogaku, 33(7), p.492 - 499, 1998/00
no abstracts in English
Tada, Kenichi; Ikehara, Tadashi; Ono, Michitaka*; Tojo, Masayuki*
no journal, ,
Comparison of the nuclear data processing code is realised using nuclear data processing code FRENDY which has been developed in JAEA. In this study, we compared the difference of the nuclear data processing codes between FRENDY and NJOY. The impact of difference between open nuclear data processing codes on neutron transport calculations were also investigated. In this presentation, the difference of the nuclear data processing method between FRENDY and NJOY and ACE verification project carried out by IAEA.
Ono, Michitaka*; Tojo, Masayuki*; Tada, Kenichi; Ikehara, Tadashi
no journal, ,
The difference of the nuclear data processing affects the difference of cross section library and neutronics calculation. This presentation explains the comparisons of the cross section libraries and neutronics calculation results.
Tada, Kenichi; Ikehara, Tadashi; Ono, Michitaka*; Tojo, Masayuki*
no journal, ,
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.
Ono, Michitaka*; Tojo, Masayuki*; Tada, Kenichi; Ikehara, Tadashi
no journal, ,
JAEA develops a nuclear data processing code FRENDY. We can compare and verify the conventional nuclear data processing code using FRENDY. In this presentation, we explain the impact of the difference of the nuclear data processing codes on the neutronics calculations using MCNP.
Ono, Michitaka*; Tojo, Masayuki*; Yamamoto, Akio*; Tada, Kenichi
no journal, ,
FRENDY-MG enables us to generate multi-group XS library. We investigated the impact of difference between multi-group nuclear data processes on nuclear calculations.
Tada, Kenichi; Yamamoto, Akio*; Endo, Tomohiro*; Chiba, Go*; Ono, Michitaka*; Tojo, Masayuki*
no journal, ,
FRENDY (From Evaluated Nuclear Data library to any application) is a nuclear data processing code for the evaluated nuclear data libraries JENDL, ENDF/B, JEFF, TENDL, and so on. The first version of FRENDY was released in 2019 as an open-source software under the 2-clause BSD license. FRENDY Ver. 1 generates ACE files which is used for the continuous energy Monte Carlo codes such as PHITS, Serpent, and MCNP. Many new modules, e.g., the multi-group neutron cross-section generation from the ACE file, are implemented in FRENDY Ver. 2. This presentation explains the characteristics of FRENDY and new capabilities implemented in FRENDY Ver. 2.
Ono, Michitaka*; Tojo, Masayuki*; Tada, Kenichi; Iwamoto, Osamu
no journal, ,
The EOLE criticality experiment is analyzed by using the newly released evaluated nuclear data library JENDL-5 for the validation. This presentation reports the impact of the Am-241 modification on the neutronics calculation.
Tojo, Masayuki*; Ono, Michitaka*; Tada, Kenichi; Iwamoto, Osamu
no journal, ,
Analysis of the KRITZ-2 criticality experiment and calculation of the effective resonance integral measured by Hellstrand are performed by using the newly released evaluated nuclear data library JENDL-5 for the validation under hot conditions.
Tada, Kenichi; Yamamoto, Akio*; Endo, Tomohiro*; Chiba, Go*; Ono, Michitaka*; Tojo, Masayuki*
no journal, ,
JAEA released the nuclear data processing code FRENDY version 2 in January 2022. This presentation explains the overview of new functions implemented in FRENDY version 2, e.g., multi-group cross section generation, uncertainty quantification for probability tables, perturbation of ACE file, and modification of evaluated nuclear data file.
Ono, Michitaka*; Tojo, Masayuki*; Tada, Kenichi; Yamamoto, Akio*
no journal, ,
The multi-group constants generation function was implemented in the nuclear data processing code FRENDY version 2 which is developed by JAEA. This function has characteristic capabilities, e.g., automatic setting of the background cross section. In this work, the multi-group constants for the BWR design code were generated using FRENDY version 2 and the differences between FRENDY version 2 and NJOY were compared.
