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JAEA Reports

Preparation of waste standards; Annual report 2022

Project Promotion Department; Radioactive Wastes Disposal Center

JAEA-Review 2023-037, 162 Pages, 2024/02

JAEA-Review-2023-037.pdf:2.66MB

For near surface disposal of radioactive wastes generated from research, industrial and medical facilities, Japan Atomic Energy Agency has discussed methods for corresponding to the technical standards on confirmation related to waste disposal, etc. From FY2022, we have established Waste Standards Committee and interim Waste Acceptance Criteria, Waste Package Confirmation Procedure, etc. have been considered. In FY2022, Waste Package Confirmation Procedures of solidified liquid waste and cement filled waste and related standards were discussed. In addition, issues of preparation of Waste Package Confirmation Procedure and rational treatment method for decommissioning wastes were considered. This annual report summarizes the results of discussion in FY2022.

JAEA Reports

Decommissioning of the Plutonium Research Building No.1 (Plan and Present Status)

Komuro, Michiyasu; Kanazawa, Hiroyuki; Kokusen, Junya; Shimizu, Osamu; Honda, Junichi; Harada, Katsuya; Otobe, Haruyoshi; Nakada, Masami; Inagawa, Jun

JAEA-Technology 2021-042, 197 Pages, 2022/03

JAEA-Technology-2021-042.pdf:16.87MB

Plutonium Research Building No.1 was constructed in 1960 for the purpose of establishing plutonium handling technology and studying its basic physical properties. Radiochemical research, physicochemical research and analytical chemistry regarding solutions and solid plutonium compounds had been doing for the research program in Japan Atomic Energy Agency (JAEA). In 1964, the laboratory building was expanded and started the researching plutonium-uranium mixed fuel and reprocessing of plutonium-based fuel, playing an advanced role in plutonium-related research in Japan. Since then, the research target has been expanded to include transplutonium elements, and it has functioned as a basic research facility for actinides. The laboratory is constructed by concrete structure and it has the second floor, equipped with 15 glove boxes and 4 chemical hoods. Plutonium Research Building No.1 was decided as one of the facilities to be decommissioned by Japan Atomic Energy Agency Reform Plan in September 2014. So far, the contamination survey of the radioactive materials in the controlled area, the decontamination of glove boxes, and the consideration of the equipment dismantling procedure have been performed as planned. The radioisotope and nuclear fuel materials used in the facility have been transfer to the other facilities in JAEA. The decommissioning of the facility is proceeding with the goal of completing by decommissioning the radiation controlled area in 2026. In this report, the details of the decommissioning plan and the past achievements are reported with the several data.

Journal Articles

Neutron diffractometer for biological macromolecule crystallography

Kurihara, Kazuo; Tanaka, Ichiro*; Niimura, Nobuo

Nihon Kessho Gakkai-Shi, 46(3), p.193 - 200, 2004/05

Neutron diffraction provides an experimental method of directly locating hydrogen atoms in proteins and nucleic acids, and the development of the neutron imaging plate (NIP) became a breakthrough event in neutron protein crystallography. A high-resolution neutron diffractometers dedicated to biological macromolecules (BIX-3, BIX-4) with the NIP have been constructed at Japan Atomic Energy Research Institute. The detailed structure of the diffractometer and the systematic procedure of the neutron diffraction experiment from the crystallization of a large single crystal to the data collection and the data processing, and the future prospect of the neutron diffractometry in proteins will be presented.

Journal Articles

Rail deployment and storage procedure and test for ITER blanket remote maintenance

Kakudate, Satoshi; Shibanuma, Kiyoshi

Fusion Engineering and Design, 65(1), p.133 - 140, 2003/01

 Times Cited Count:11 Percentile:59.28(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of revised procedure on determining large excess reactivity of operating reactor; Fuel addition method

Nagao, Yoshiharu; Hosoya, Toshiaki; Kaneko, Yoshihiko*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(2), p.153 - 163, 2002/06

no abstracts in English

Journal Articles

Mock-up test of remote controlled dismantling apparatus for large-sized vessels

Kimura, Masanori; Myodo, Masato; Okane, Shogo; Miyajima, Kazutoshi

Proceeding of International Waste Management Symposium 2002 (WM '02) (CD-ROM), 14 Pages, 2002/00

no abstracts in English

Journal Articles

Development of remote dismantling systems for decommissioning of nuclear facilities

Tachibana, Mitsuo; Shimada, Taro; Yanagihara, Satoshi

Proceedings of International Waste Management Symposium '00 (Waste Manegement '00) (CD-ROM), 9 Pages, 2000/02

no abstracts in English

Journal Articles

Application of JACOS to evaluation of NPP emergency operating procedure

Yoshida, Kazuo

Proceedings of Cognitive Systems Engineering in Process Control (CSEPC 2000), p.83 - 90, 2000/00

no abstracts in English

Journal Articles

Analysis of remote dismantling activities in decommissioning of nuclear facilities

Tachibana, Mitsuo; Uchikoshi, Tadaaki; Yanagihara, Satoshi

Proceedings of 7th International Conference on Radioactive Waste Management and Environmental Remediation (ICEM '99) (CD-ROM), p.6 - 0, 1999/00

no abstracts in English

JAEA Reports

Design of ITER shielding blanket

Furuya, Kazuyuki; Sato, Satoshi; Hatano, Toshihisa; *; Kitamura, Kazunori*; Miura, H.*; *; Kuroda, Toshimasa*; Takatsu, Hideyuki

JAERI-Tech 97-022, 113 Pages, 1997/05

JAERI-Tech-97-022.pdf:3.42MB

no abstracts in English

JAEA Reports

Quality control of the software in the JT-60 computer control system

*; Kurihara, Kenichi; Kimura, Toyoaki

JAERI-M 90-114, 28 Pages, 1990/07

JAERI-M-90-114.pdf:1.09MB

no abstracts in English

Journal Articles

Desorption behavior of plutonium from anion-exchange resin with HNO$$_{3}$$-HI mixed acid solution

Usuda, Shigekazu; Sakurai, Satoshi; Hirata, Masaru; Umezawa, Hirokazu

Sep. Sci. Technol., 25(11-12), p.1225 - 1237, 1990/00

 Times Cited Count:1 Percentile:27.36(Chemistry, Multidisciplinary)

no abstracts in English

JAEA Reports

JAEA Reports

Shielding Design of the Upgraded JRR-3 Research Reactor

; ; ; ; *

JAERI-M 85-065, 15 Pages, 1985/06

JAERI-M-85-065.pdf:0.68MB

no abstracts in English

Journal Articles

Effect of Fe-56 anisotropic scattering on neutron penetration

; ; *

Journal of Nuclear Science and Technology, 20(5), p.435 - 438, 1983/00

 Times Cited Count:0 Percentile:0.29(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Solution of three-dimensional neutron transport equation by double finite element method

; ; *

Journal of Nuclear Science and Technology, 20(7), p.620 - 623, 1983/00

 Times Cited Count:3 Percentile:54.47(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Opened Tapes of ROSA-II Test Data; AnUserManualforOpendTapes

; ; *

JAERI-M 8287, 55 Pages, 1979/06

JAERI-M-8287.pdf:1.96MB

no abstracts in English

Journal Articles

Cost-benefit analysis of shielding for pipes inspections at JPDR

; ; ;

Hoken Butsuri, 14(3), p.185 - 192, 1979/00

no abstracts in English

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