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Fukahori, Tokio
INDC(JPN)-210 (Internet), 5 Pages, 2023/10
The 
U(n,f) cross section values were not correctly compiled in the ENDF format, and wrong values are disseminated in the JENDL/HE-2007 file. The high energy part of the U(n,f) cross section for the JENDL/HE-2007 library was evaluated by using the results of the FISCAL code. The correct U(n,f) cross section values of the JENDL/HE-2007 library above 200 MeV is given in this report.
Ni and Zr at 0.4, 1.3, 2.2, and 3.0 GeVTakeshita, Hayato*; Meigo, Shinichiro; Matsuda, Hiroki*; Iwamoto, Hiroki; Nakano, Keita; Watanabe, Yukinobu*; Maekawa, Fujio
Nuclear Instruments and Methods in Physics Research B, 527, p.17 - 27, 2022/09
Times Cited Count：3 Percentile：50.96(Instruments & Instrumentation)To improve accuracy of nuclear design of accelerator driven nuclear transmutation systems and so on, nuclide production cross sections on Ni and Zr were measured for GeV energy protons. The measured results were compared with PHITS calculations, JENDL/HE-2007 and so on.
Takeshita, Hayato*; Meigo, Shinichiro; Matsuda, Hiroki*; Iwamoto, Hiroki; Nakano, Keita; Watanabe, Yukinobu*; Maekawa, Fujio
Nuclear Instruments and Methods in Physics Research B, 511, p.30 - 41, 2022/01
Times Cited Count：6 Percentile：64.12(Instruments & Instrumentation)Nuclide production cross sections for proton-induced reactions on Mn and Co at incident energies of 1.3, 2.2, and 3.0 GeV were measured by the activation method at the J-PARC. In total, 143 production cross sections of reaction products were obtained. Among them, the cross sections of 
Mn(p,X)
S and Mn(p,X)
Ar were measured for the first time. The stable proton beam and well established beam monitoring system contributed to the reduction of the systematic uncertainties to typically less than 5%, which was better than those of the previous data. To examine the prediction capabilities of spallation reaction models and evaluated data library, the measured data were compared with the spallation reaction models in PHITS (INCL4.6/GEM, etc.), INCL++/ABLA07, and the JENDL/HE-2007 library. The comparison of the mean square deviation factors indicated that both INCL4.6/GEM and JENDL/HE-2007 showed better agreement with the measured data than the others.
Takeshita, Hayato; Meigo, Shinichiro; Matsuda, Hiroki; Iwamoto, Hiroki; Maekawa, Fujio; Watanabe, Yukinobu*
JPS Conference Proceedings (Internet), 33, p.011045_1 - 011045_6, 2021/03
To improve accuracy of nuclear design of accelerator driven nuclear transmutation systems, nuclide production cross sections on Ni and Zr, which were candidate materials to be used in ADS, were measured for GeV energy protons. The measured results were compared with PHITS calculations and JENDL/HE-2007.
Matsuda, Hiroki; Meigo, Shinichiro; Iwamoto, Hiroki
Journal of Nuclear Science and Technology, 55(8), p.955 - 961, 2018/08
Times Cited Count：7 Percentile：45.59(Nuclear Science & Technology)We have started an experimental program to measure activation cross sections systematically in the proton-induced spallation reaction in structural materials commonly used in high-intensity proton accelerator-based facilities, such as Japan Proton Accelerator Research Complex (J-PARC). As the first step of the program, aluminum (Al) was chosen to verify the adequacy of the measurement technique implemented in a J-PARC proton beam environment because data of Al have been relatively well studied both by experimental measurement and simulation. Activation cross sections of 
Be, 
Na, and 
Na in Al were measured at proton energy points from 0.4, 1.3, 2.2 to 3.0 GeV, which could be delivered smoothly from the synchrotron. The validity of experimental data has been verified by introducing an effective proton numbers determination procedure. We compared the measured data with existing experimental data, the evaluated data (JENDL-HE/2007), and the calculations with several intra-nuclear cascade models by the Particle and Heavy Ion Transport code System (PHITS) code. Although the experimental data agreed with JENDL-HE/2007, the calculations underestimated about 40%. This could come from the evaporation model (generalized evaporation model) being implemented in the PHITS code. We found that the calculations agreed with the experimental data by an upgraded PHITS code.
Meigo, Shinichiro; Matsuda, Hiroki; Iwamoto, Hiroki
Proceedings of 13th International Topical Meeting on Nuclear Applications of Accelerators (AccApp '17) (Internet), p.396 - 402, 2018/05
no abstracts in English
Meigo, Shinichiro; Nishikawa, Masaaki; Iwamoto, Hiroki; Matsuda, Hiroki
EPJ Web of Conferences, 146, p.11039_1 - 11039_4, 2017/09
Times Cited Count：2 Percentile：77.83(Nuclear Science & Technology)no abstracts in English
Konno, Chikara; Ochiai, Kentaro; Sato, Satoshi; Ota, Masayuki
Fusion Engineering and Design, 98-99, p.2178 - 2181, 2015/10
Times Cited Count：8 Percentile：51.03(Nuclear Science & Technology)We have analyzed the iron and concrete shielding experiments with the 40 and 65 MeV neutron sources at TIARA in Japan Atomic Energy Agency with the latest high-energy nuclear data libraries, JENDL/HE-2007, ENDF/B-VII.1 and FENDL-3.0. The Monte Carlo code MCNP-5 and ACE files of JENDL/HE-2007, ENDF/B-VII.1 and FENDL-3.0, which were supplied from JAEA, BNL and IAEA, respectively, were used for this analysis. The followings are found out from the results. (1) The calculations with JENDL/HE-2007 agree with all the measured ones well; (2) Those with ENDF/B-VII.1 tend to overestimate the measured ones with the thickness of the assemblies largely; (3) Those with FENDL-3.0 agree with the measured ones well for the iron experiment, while they overestimate the measured ones well for the concrete experiment largely. Some data in ENDF/B-VII.1 and FENDL-3.0 should be revised.
Konno, Chikara
no journal, ,
We examined the ACE files of the Fusion Evaluated Nuclear Data Library FENDL-3.2b in detail and found that damage production energy cross section data and proton ACE files had problems. It was pointed out that the damage production energy cross section data above 20 MeV of FENDL-3.2b from JENDL-4.0/HE and those above a few MeV of FENDL-3.2b from JEFF-3.1.1 were too small, which was solved by replacing them with JENDL-5 and JEFF-3.2 in the next FENDL, respectively. It was also proposed to reproduce the proton ACE files of FENDL-3.2b from JENDL/HE-2007 for the next FENDL with the nuclear data processing code NJOY2016 modified for JENDL-5, because the Monte Carlo code MCNP6.2 could not treat secondary neutron production data in the proton ACE files of FENDL-3.2b from JENDL/HE-2007 adequately.
