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Journal Articles

Measurement of displacement cross section for proton in the kinetic energy range from 0.4 GeV to 3 GeV

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.

Journal Articles

Measurement of displacement cross section of structural materials utilized in the proton accelerator facilities with the kinematic energy above 400 MeV

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:0.1

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 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.

Journal Articles

Development of the evaluation methodology for the material relocation behavior in the core disruptive accident of sodium-cooled fast reactors

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

AA2015-0794.pdf:2.46MB

 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.

Journal Articles

Ion beam breeding of rice for the mutation breeding project of the Forum for Nuclear Cooperation in Asia (FNCA)

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

Journal Articles

Ion beam breeding of rice for the mutation breeding project of the Forum for Nuclear Cooperation in Asia (FNCA)

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

Journal Articles

Ion beam breeding of rice for the mutation breeding project of the Forum for Nuclear Cooperation in Asia (FNCA)

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

Journal Articles

Photoperiod-insensitive mutants with shorter plant height identified in the M1 generation of rice irradiated with carbon ion beams

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

Journal Articles

Ion beam irradiation on rice seeds for the Mutation Breeding Project of the Forum of Nuclear Cooperation in Asia (FNCA)

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

Journal Articles

Ion beam irradiation on rice seeds for the Mutation Breeding Project of the Forum for Nuclear Cooperation in Asia (FNCA)

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

Journal Articles

Ion beam irradiation with rice seeds for the Mutation Breeding Project of the Forum for Nuclear Cooperation in Asia (FNCA)

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

JAEA Reports

Investigation of the long term corrosion resistance of the overpack FY2006 (Contract research)

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

JAEA-Research-2007-086.pdf:5.96MB

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.

JAEA Reports

Investigation of the long term corrosion resistance of the overpack (Contract research)

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

JAEA-Research-2006-058.pdf:10.86MB

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.

JAEA Reports

Investigation of the Long Term Stability and Corrosion Resistance of Engineering Barriers

Aoyama, Eri*; Tachikawa, Hirokazu*; Shimizu, Akihiko*

JNC TJ8400 2004-034, 442 Pages, 2005/03

JNC-TJ8400-2004-034.pdf:18.48MB

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.

JAEA Reports

Investigations of and Technical Reviews on the Reliability of Prediction for Migration Behavior of Radionuclides (H.16)

Sano, Eri*; Tachikawa, Hirokazu*; Shimizu, Akihiko*

JNC TJ8420 2004-004, 342 Pages, 2005/02

JNC-TJ8420-2004-004.pdf:15.39MB

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

JAEA Reports

Investigation and Technical Reviews of the Long Term Stability and Corrosion Resistance of Engineering Barriers

Tachikawa, Hirokazu*

JNC TJ8400 2003-082, 240 Pages, 2004/03

JNC-TJ8400-2003-082.pdf:13.81MB

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.

JAEA Reports

Investigations and Technical Reviews on the Reliability of Prediction for Migration Behavior of Radionuclides(H15)

Tachikawa, Hirokazu*

JNC TJ8420 2003-002, 280 Pages, 2004/02

JNC-TJ8420-2003-002.pdf:9.17MB

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.

JAEA Reports

None

Tachikawa, Hirokazu*

JNC TJ8420 2002-007, 227 Pages, 2003/02

JNC-TJ8420-2002-007.pdf:15.85MB

no abstracts in English

JAEA Reports

None

Tachikawa, Hirokazu*

JNC TJ8420 2001-011, 167 Pages, 2002/02

JNC-TJ8420-2001-011.pdf:8.01MB

no abstracts in English

JAEA Reports

None

Sato, Hideharu*

JNC TJ8420 2001-001, 126 Pages, 2001/03

JNC-TJ8420-2001-001.pdf:4.09MB

no abstracts in English

72 (Records 1-20 displayed on this page)