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Journal Articles

Evaluation of deuteron nuclear data on iron isotopes

Nakayama, Shinsuke

Fusion Engineering and Design, 230, p.115866_1 - 115866_6, 2026/09

 Times Cited Count:0

In fusion reactors beyond the experimental reactor stage, reactor materials are exposed to a large flux of high-energy neutrons. The International Fusion Materials Irradiation Facility (IFMIF) is a material irradiation testing facility that utilizes an accelerator-based neutron source to assess the integrity of such reactor materials. In IFMIF, neutrons are generated by irradiating a liquid lithium target with a 40 MeV deuteron beam. For evaluating radioactivity production and designing radiation shielding in IFMIF and various precursor facilities, nuclear data on deuteron-induced reactions for iron, a primary structural material of accelerators, are required. These data include the production cross-sections of radioactive isotopes such as Mn-54, Co-56, and Co-57, as well as the energy and angular distributions of emitted neutrons. However, high-precision deuteron nuclear data for iron isotopes have not been available until now. We have previously evaluated and compiled deuteron nuclear data for light nuclei (Li-6,7, Be-9, C-12,13) for neutron source design and released them as JENDL/DEU-2020. Subsequently, we incorporated data for Al-27, Cu-63,65, and Nb-93 into the above data and published it as the deuteron sublibrary of the Japanese general-purpose nuclear reaction library JENDL-5. In this study, we evaluated deuteron nuclear data for the stable isotopes of iron (Fe-54,56,57,58). The evaluation was conducted using DEURACS, a nuclear reaction calculation code specifically designed for deuteron-induced ones, as in our previous work. As a result, the evaluated data successfully reproduced not only the residual nucleus production cross-sections but also the neutron emission spectra. In this presentation, we will provide an overview of the evaluation methodology and discuss the obtained results.

Journal Articles

The JT-60 machine upgrade and development towards the next step in Japan

Shirakata, Hirofumi

Fusion Engineering and Design, 14, p.7 - 19, 1991/00

 Times Cited Count:1 Percentile:19.58(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Cryogenic system design and its component development for Fusion Experimental Reactor(FER)

Kato, Takashi; Tada, Eisuke; Hiyama, Tadao; Kawano, Katsumi; ; ; ; ; Shimamoto, Susumi

Fusion Technology 1990, p.1535 - 1539, 1991/00

no abstracts in English

Journal Articles

Fabrication and test of the Nb$$_{3}$$Sn Demo Poloidal Coil(DPC-EX)

Ando, Toshinari; Hiyama, Tadao; Tsuji, Hiroshi; Takahashi, Yoshikazu; Nishi, Masataka; Tada, Eisuke; Yoshida, Kiyoshi; Okuno, Kiyoshi; Koizumi, Koichi; Nakajima, Hideo; et al.

Fusion Technology 1990, p.243 - 247, 1991/00

no abstracts in English

Journal Articles

Advanced structural materials developed for the first wall

; Kiuchi, Kiyoshi; Hishinuma, Akimichi

Fusion Technology 1990, p.443 - 447, 1991/00

no abstracts in English

Journal Articles

Mechanical test ofsuperconducting magnet system for fusion experimental reactor

Sugimoto, Makoto; Yoshida, Kiyoshi; Hasegawa, Mitsuru*; Koizumi, Koichi; Nakajima, Hideo; ; ; ; Yasukawa, Yukio*; Sasaki, Takashi*; et al.

Fusion Technology 1990, p.1530 - 1534, 1991/00

no abstracts in English

Journal Articles

New digital control systems of poloidal field power supplies for JT-60 upgrade

Matsuzaki, Yoshimi; Aoyagi, Tetsuo; ; ; ;

Fusion Technology 1990, p.1482 - 1486, 1991/00

no abstracts in English

Journal Articles

Construction and testing of the new multijunction LHRF launcher for JT-60 upgrade

Seki, Masami; Ikeda, Yoshitaka; ; Imai, Tsuyoshi; ; Yokokura, Kenji; Sawahata, Masayuki; Suganuma, Kazuaki; Sato, Minoru; ; et al.

Fusion Technology 1990, p.1060 - 1064, 1991/00

no abstracts in English

Journal Articles

Upgrade of JT-60 ICRF heating system

Fujii, Tsuneyuki; ; Moriyama, Shinichi; Saigusa, Mikio; ; ; Terakado, Masayuki; ; ; ; et al.

Fusion Technology 1990, Vol.1, p.1171 - 1175, 1991/00

no abstracts in English

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