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Journal Articles

Quantitative X-ray diffraction analysis of solute-enriched stacking faults in $$hcp$$-Mg alloys based on peak asymmetry analysis

Egusa, Daisuke*; Manabe, Ryo*; Kawasaki, Takuro; Harjo, S.; Sato, Shigeo*; Abe, Eiji*

Materials Today Communications (Internet), 31, p.103344_1 - 103344_6, 2022/06

 Times Cited Count:4 Percentile:62.5(Materials Science, Multidisciplinary)

JAEA Reports

Case studies of radiation dose assessment in emergency situation of nuclear facilities

Kawasaki, Masatsugu; Nakajima, Junya; Yoshida, Keisuke; Kato, Saori; Nishino, Sho; Nozaki, Teo; Nakagawa, Masahiro; Tsunoda, Junichi; Sugaya, Yuki; Hasegawa, Rie; et al.

JAEA-Data/Code 2017-004, 57 Pages, 2017/03

JAEA-Data-Code-2017-004.pdf:2.34MB

In emergency situation of nuclear facilities, we need to estimate the radiation dose due to radiation and radioactivity to grasp the influence range of the accident in the early stage. Therefore, we prepare the case studies of dose assessment for public exposure dose and personal exposure dose and contribute them to emergency procedures. This document covers about accidents of nuclear facilities in Nuclear Science Research Institute and past accident of nuclear power plant, and it can be used for inheritance of techniques of emergency dose assessment.

Journal Articles

Symposium on "Science of nuclear fuel cycle and backend; Research and education" with a memory of Professor Joonhong Ahn, the University of California, Berkeley

Nakayama, Shinichi; Okumura, Masahiko*; Nagasaki, Shinya*; Enokida, Yoichi*; Umeki, Hiroyuki*; Takase, Hiroyasu*; Kawasaki, Daisuke*; Hasegawa, Shuichi*; Furuta, Kazuo*

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 23(2), p.131 - 148, 2016/12

A symposium "Science of nuclear fuel cycle and backend - Research and education -" was held at the Univer-sity of Tokyo in June 25, 2016. This aimed at developing the research on nuclear fuel cycle and backend. The time and the number of participants of the symposium were limited, but the active discussion was conducted, and the common perception for the future was shared among the experienced participants in those fields. This paper provides the discussions made in the symposium, and also, as a memory to Professor Ahn, the University of California, Berkeley, his prominent achievements in academic research and education.

JAEA Reports

Operating experiences since rise-to-power test in High Temperature Engineering Test Reactor (HTTR)

Tochio, Daisuke; Watanabe, Shuji; Motegi, Toshihiro; Kawano, Shuichi; Kameyama, Yasuhiko; Sekita, Kenji; Kawasaki, Kozo

JAEA-Technology 2007-014, 62 Pages, 2007/03

JAEA-Technology-2007-014.pdf:9.74MB

The rise-to-power test of the High Temperature Engineering Test Reactor (HTTR) was begun in April 2000. The reactor thermal power of 30 MW, which is the maximum thermal power of the HTTR, and the reactor outlet coolant temperature of 850$$^{circ}$$C in normal operation was achieved in middle of December 2001. After that reactor thermal power of 30 MW a reactor outlet coolant temperature of 950$$^{circ}$$C was achieved in the final rise-to-power test at April 2004. After receiving the operation permit, the safety demonstration tests were conducted to demonstrate inherent safety features of the HTGRs. This paper summarizes the HTTR operating experiences for five years since rise-to-power test that were catalogued into three categories, (1) Operating experience pertaining to new gas cooled reactor design, (2) Operating experience for improvement of the performance, (3) Operating experience due to fail of system and components.

JAEA Reports

The Approaches of safety design and safety evaluation at HTTR (High Temperature Engineering Test Reactor)

Iigaki, Kazuhiko; Saikusa, Akio; Sawahata, Hiroaki; Shinozaki, Masayuki; Tochio, Daisuke; Homma, Fumitaka; Tachibana, Yukio; Iyoku, Tatsuo; Kawasaki, Kozo; Baba, Osamu*

JAEA-Review 2006-010, 90 Pages, 2006/07

JAEA-Review-2006-010.pdf:5.65MB

Gas Cooled Reactor has long history of nuclear development, and High Temperature Gas Cooled Reactor (HTGR) has been expected that it can be supply high temperature energy to chemical industry and to power generation from the points of view of the safety, the efficiency, the environment and the economy. The HTGR design is tried to installed passive safety equipment. The current licensing review guideline was made for a Low Water Reactor (LWR) on safety evaluation therefore if it would be directly utilized in the HTGR it needs the special consideration for the HTGR. This paper describes that investigation result of the safety design and the safety evaluation traditions for the HTGR, comparison the safety design and safety evaluation feature for the HTGT with it's the LWR, and reflection for next HTGR based on HTTR operational experiment.

Oral presentation

Development of the technology basis for holistic waste management taking into consideration whole fuel cycle system, 3; Electronic-performance analysis report to support nuclide migration analysis and report writing

Koo, Shigeru; Makino, Hitoshi; Umeki, Hiroyuki; Hioki, Kazumasa; Kawasaki, Daisuke*; Tachibana, Shoko*

no journal, , 

no abstracts in English

Oral presentation

Application of VRdose for the decommissioning

Taruta, Yasuyoshi; Kawasaki, Daisuke*; Yanagihara, Satoshi*

no journal, , 

no abstracts in English

Oral presentation

Knowledge representation in decommissioning knowledge management

Taruta, Yasuyoshi; Kawasaki, Daisuke*; Yanagihara, Satoshi*; Iguchi, Yukihiro; Koda, Yuya; Tomoda, Koichi

no journal, , 

no abstracts in English

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