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Meigo, Shinichiro; Matsuda, Hiroki; Iwamoto, Yosuke; Yoshida, Makoto*; Hasegawa, Shoichi; Maekawa, Fujio; Iwamoto, Hiroki; Nakamoto, Tatsushi*; Ishida, Taku*; Makimura, Shunsuke*
JPS Conference Proceedings (Internet), 33, p.011050_1 - 011050_6, 2021/03
R&D of the beam window is crucial in the ADS, which serves as a partition between the accelerator and the target region. Although the displacement per atom (DPA) is used to evaluate the damage on the window, experimental data on the displacement cross section is scarce in the energy region above 20 MeV. We started to measure the displacement cross section for the protons in the energy region between 0.4 to 3 GeV. The displacement cross section can be derived by resistivity change divided by the proton flux and the resistivity change per Frankel pair on cryo-cooled sample to maintain damage. Experiments were conducted at the 3 GeV proton synchrotron at the J-PARC Center, and aluminum and copper was used as samples. As a result of comparison between the present experiment and the calculation of the NRT model, which is widely used for calculation of the displacement cross section, it was found that the calculation of the NRT model overestimated the experiment by about 3 times.
Meigo, Shinichiro; Matsuda, Hiroki; Iwamoto, Yosuke; Yoshida, Makoto*; Hasegawa, Shoichi; Maekawa, Fujio; Iwamoto, Hiroki; Nakamoto, Tatsushi*; Ishida, Taku*; Makimura, Shunsuke*
EPJ Web of Conferences, 239, p.06006_1 - 06006_4, 2020/09
Times Cited Count:0 Percentile:0.1R&D of the beam window is crucial in the ADS, which serves as a partition between the accelerator and the target region. Although the displacement per atom (DPA) is used to evaluate the damage on the window, experimental data on the displacement cross section is scarce in the energy region above 20 MeV. We started to measure the displacement cross section for the protons in the energy region between 0.4 to 3 GeV. The displacement cross section can be derived by resistivity change divided by the proton flux and the resistivity change per Frankel pair on cryo-cooled sample to maintain damage. Experiments were conducted at the 3 GeV proton synchrotron at the J-PARC Center, and copper was used as samples. As a result of comparison between the present experiment and the calculation of the NRT model, which is widely used for calculation of the displacement cross section, it was found that the calculation of the NRT model overestimated the experiment by about 3 times.
Tobita, Yoshiharu; Kamiyama, Kenji; Tagami, Hirotaka; Matsuba, Kenichi; Suzuki, Toru; Isozaki, Mikio; Yamano, Hidemasa; Morita, Koji*; Guo, L.*; Zhang, B.*
Journal of Nuclear Science and Technology, 53(5), p.698 - 706, 2016/05
Times Cited Count:19 Percentile:88.97(Nuclear Science & Technology)The in-vessel retention (IVR) of core disruptive accident (CDA) is of prime importance in enhancing safety characteristics of sodium-cooled fast reactors (SFRs). In the CDA of SFRs, molten core material relocates to the lower plenum of reactor vessel and may impose significant thermal load on the structures, resulting in the melt through of the reactor vessel. In order to enable the assessment of this relocation process and prove that IVR of core material is the most probable consequence of the CDA in SFRs, a research program to develop the evaluation methodology for the material relocation behavior in the CDA of SFRs has been conducted. This program consists of three developmental studies, namely the development of the analysis method of molten material discharge from the core region, the development of evaluation methodology of molten material penetration into sodium pool, and the development of the simulation tool of debris bed behavior.
Tanaka, Atsushi; Hase, Yoshihiro; Ono, Yutaka; Ishikawa, Hidetaka*; Koike, Aki*
JAEA-Review 2015-022, JAEA Takasaki Annual Report 2014, P. 96, 2016/02
no abstracts in English
Tanaka, Atsushi; Hase, Yoshihiro; Ono, Yutaka; Ishikawa, Hidetaka*; Koike, Aki*
JAEA-Review 2014-050, JAEA Takasaki Annual Report 2013, P. 107, 2015/03
no abstracts in English
Tanaka, Atsushi; Nozawa, Shigeki; Hase, Yoshihiro; Narumi, Issey*; Ishikawa, Hidetaka*; Koike, Aki*
JAEA-Review 2013-059, JAEA Takasaki Annual Report 2012, P. 103, 2014/03
Azad, M. A. K.*; Mazumdar, M. N. N.*; Chaki, A. K.*; Ali, M.*; Hakim, M. L.*; Mamun, A. N. K.*; Hase, Yoshihiro; Nozawa, Shigeki; Tanaka, Atsushi; Koike, Aki*; et al.
SABRAO Journal of Breeding and Genetics, 45(2), p.179 - 186, 2013/06
no abstracts in English
Tanaka, Atsushi; Nozawa, Shigeki; Hase, Yoshihiro; Narumi, Issei; Ishikawa, Hidetaka*; Koike, Aki*
JAEA-Review 2012-046, JAEA Takasaki Annual Report 2011, P. 96, 2013/01
Tanaka, Atsushi; Nozawa, Shigeki; Hase, Yoshihiro; Narumi, Issei; Ishikawa, Hidetaka*; Koike, Aki*
JAEA-Review 2011-043, JAEA Takasaki Annual Report 2010, P. 101, 2012/01
Tanaka, Atsushi; Nozawa, Shigeki; Hase, Yoshihiro; Narumi, Issei; Ishikawa, Hidetaka*; Koike, Aki*
JAEA-Review 2010-065, JAEA Takasaki Annual Report 2009, P. 61, 2011/01
Tachikawa, Hirokazu*; Kawakubo, Fumie*; Shimizu, Akihiko*; Shibata, Toshio*; Azumi, Kazuhisa*; Inoue, Hiroyuki*; Sugimoto, Katsuhisa*; Tsuru, Toru*; Fujimoto, Shinji*
JAEA-Research 2007-086, 74 Pages, 2008/02
The corrosion life time of the overpack has been investigated on the basis of experimental data and past research, assuming the ranging geological environment of Japan. However, some subject for the realization of the overpack design, such as the behavior of the overpack under high pH conditions, the behavior of the overpack with change of near-field environmental condition and the corrosion behavior of the welds have still been left. To take into account these conditions, expert committee composed of metal corrosion science experts were established in the Nuclear Safety Research Association and past research outcomes and the theory of safety assessment for long term corrosion resistance were investigated from the view points of metal corrosion science.
Tachikawa, Hirokazu*; Kawakubo, Fumie*; Shimizu, Akihiko*; Shibata, Toshio*; Sugimoto, Katsuhisa*; Seo, Masahiro*; Tsuru, Toru*; Fujimoto, Shinji*; Inoue, Hiroyuki*
JAEA-Research 2006-058, 80 Pages, 2006/10
The Japan Nuclear Cycle Development Institute submitted "Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan" to the Japanese government. This report contains investigations of the corrosion life time of the overpack on the basis of experimental data and past research, assuming the ranging geological environment of Japan. However some subjects, such as the behavior of the overpack under high pH conditions and the behavior of the engineering barrier with change of near-field environmental condition with time for promoting reliability have still been left. To take into account these conditions, expert committee composed of metal corrosion science experts were established in the Nuclear Safety Research Association and past research outcomes and the theory of safety assessment were investigated from the view points of long term stability and corrosion resistance of engineering barrier.
Saito, Kimiaki
Genankyo Dayori, (205), 11 Pages, 2005/04
no abstracts in English
Aoyama, Eri*; Tachikawa, Hirokazu*; Shimizu, Akihiko*
JNC TJ8400 2004-034, 442 Pages, 2005/03
The Japan Nuclear Cycle Development Institute submitted 'Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan' to the Japanese government. This report contains investigations of the long term behavior of alteration of bentonite, and of the corrosion life time of overpack on the basis of experimental data and past research, assuming the ranging geological environment of Japan. However some subjects, such as the behavior of the bentonite and overpack under high pH conditions and the behavior of the engineering barrier with change of near-field environmental condition with time for promoting reliability have still been left.To take into account these conditions, expert committees composed of clay science and metal corrosion science experts were established in the Nuclear Safety Research Association and past research outcomes and the theory of safety assessment were investigated from the view points of long term stability and corrosion resistance of engineering buffer materials.
Sano, Eri*; Tachikawa, Hirokazu*; Shimizu, Akihiko*
JNC TJ8420 2004-004, 342 Pages, 2005/02
The research plan of the radionuclides migration drawn up by Japan Nuclear Fuel Cycle Development Institute and its' research outcome were reviewed comprehensively by an expert committee established in Nuclear Safety Research Association. Also, experimental investigations for the migration behavior of actinide elements and fission products in engineering barrier and natural barrier media, and for solution chemistry of them were carried out and discussed by the committee, in order to enhance the reliability of prediction for migration behavior of radionuclides. The subjects investigated by the expert committee are as follows; (1)Diffusion and electromigration behavior of Plutonium in bentnite under reducing condition (2)Numerical analysis of distribution coefficients of nuclides in compacted bentonite using surface complexization model (3)Radioactive disequilibrium of decay series nuclides in natural water and various materials (4)Research on complexation reactions of f - elements
Tachikawa, Hirokazu*
JNC TJ8400 2003-082, 240 Pages, 2004/03
The Japan Nuclear Fuel Cycle Development Institute submitted 'Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan' to the Japanese government. This report contains investigations of the long term behavior of alteration of bentonite, and of the corrosion life time of overpack on the basis of experimental data and past research, assuming the ranging geological environment of Japan. However some subjects, such as the behavior of the bentonite and overpack under high pH conditions and the behavior of the engineering barrier with change of near-field environmental condition with time for promoting reliability have still been left. To take into account these conditions, expert committees composed of clay science and metal corrosion science experts were established in the Nuclear Safety Research Association and past research outcomes and the theory of safety assessment were investigated and technically reviewed from the view points of long term stability and corrosion resistance of engineering buffer materials.
Tachikawa, Hirokazu*
JNC TJ8420 2003-002, 280 Pages, 2004/02
The research plan of the validation on effects of colloids and organic materials drawn up by the Japan Nuclear Fuel Cycle Development Institute and its' research outcome were reviewed comprehensively by an expert committee established in the Nuclear Safety Research Association.