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Journal Articles

Testing of criticality accident alarm system detectors to pulsed radiation at TRACY

Tsujimura, Norio; Yoshida, Tadayoshi; Sanada, Yukihisa

JPS Conference Proceedings (Internet), 24, p.011013_1 - 011013_6, 2019/01

Journal Articles

Study of experimental core configuration of the modified STACY for measurement of criticality characteristics of fuel debris

Gunji, Satoshi; Tonoike, Kotaro; Izawa, Kazuhiko; Sono, Hiroki

Progress in Nuclear Energy, 101(Part C), p.321 - 328, 2017/11

Criticality safety of fuel debris, particularly MCCI (Molten-Core-Concrete-Interaction) products, is one of the major safety issues for decommissioning of Fukushima Daiichi Nuclear Power Station. Criticality or subcriticality condition of the fuel debris is still uncertain; its composition, location, neutron moderation, etc. are not yet confirmed. The effectiveness of neutron poison in cooling water is also uncertain for use as a criticality control of fuel debris. A database of computational models is being built by Japan Atomic Energy Agency (JAEA), covering a wide range of possible conditions of such composition, neutron moderation, etc., to facilitate assessing criticality characteristics once fuel debris samples are taken and their conditions are known. The computational models also include uncertainties which are to be clarified by critical experiments. These experiments are planned and will be conducted by JAEA with the modified STACY (STAtic experiment Critical facilitY) and samples to simulate fuel debris compositions. Each of the samples will be cladded by a zircalloy tube whose outer shape is compatible with the fuel rod of STACY and loaded into an array of the fuel rods. This report introduces a study of experimental core configurations to measure the reactivity worth of samples simulating MCCI products. Parameters to be varied in the computation models for the experimental series are:(1) Uranium dioxide with $$^{235}$$U enrichments of 3, 4, and 5 wt.%; (2) Concrete volume fraction in the samples of 0, 20, 40, 60, and 80%; and (3) Porosity of the samples filled from 0 to 80% where the sample void is filled with water. It is concluded that the measurement is feasible in both under- and over-moderated conditions. Additionally, the required amount of samples was estimated.

Journal Articles

Prolonged stoppage of research reactors and critical assemblies affects human resource development

Uesaka, Mitsuru*; Mineo, Hideaki

Nippon Genshiryoku Gakkai-Shi, 58(8), p.468 - 473, 2016/08

All the research reactors and critical assemblies (hereinafter RRCAs) in Japan are stopped in order to fulfil the new regulatory requirements, which were reinforced after the accident at the Tokyo Electric Power Company's Fukushima Daiichi Nuclear Power Station. These RRCAs have played important roles in the areas of human resource development, academic research, medical and industrial application of nuclear technology. Prolonged stoppage of RRCAs affects adversely those activities. Atomic Energy Society of Japan set up a group to discuss this issue. The group has shown a proposal that the roles of the RRCAs, which are indispensable facilities to nuclear human resource development, should be placed positively in the energy policy and the science and technology policy of the country.

JAEA Reports

Conceptual study of transmutation experimental facility, 3; Study on transmutation physics experiment facility

Oigawa, Hiroyuki; Maekawa, Fujio; Meigo, Shinichiro; Kasugai, Yoshimi; Tsujimoto, Kazufumi; Nishihara, Kenji; Sasa, Toshinobu; Konno, Chikara; Kai, Tetsuya; Ikeda, Yujiro

JAERI-Tech 2002-037, 220 Pages, 2002/03

JAERI-Tech-2002-037.pdf:11.09MB

no abstracts in English

Journal Articles

Experiment for accelerator-driven transmutation

Oigawa, Hiroyuki

Nippon Butsuri Gakkai-Shi, 56(10), p.749 - 754, 2001/11

no abstracts in English

JAEA Reports

Conceptual study of transmutation experimental facility, 1; Outline of transmutation physics experiment facility

Oigawa, Hiroyuki; Ikeda, Yujiro; Sasa, Toshinobu; Meigo, Shinichiro; Takano, Hideki; Tsujimoto, Kazufumi; Nishihara, Kenji

JAERI-Tech 2000-062, 64 Pages, 2000/09

JAERI-Tech-2000-062.pdf:4.25MB

no abstracts in English

JAEA Reports

Construction of STACY(Static Experiment Critical Facility)

Murakami, Kiyonobu; ; Hirose, Hideyuki; ; *; *; Sakuraba, Koichi; ; ; *; et al.

JAERI-Tech 98-033, 70 Pages, 1998/08

JAERI-Tech-98-033.pdf:2.25MB

no abstracts in English

Journal Articles

Decommissioning of the critical facility JMTRC

Takeda, Takashi; Komukai, Bunsaku; ; ; Fujiki, Kazuo; Ooka, Norikazu

Dekomisshoningu Giho, (17), p.55 - 62, 1997/12

no abstracts in English

JAEA Reports

Educational reactor-physics experiments with the critical assembly TCA

*; *; *; Suzaki, Takenori; Horiki, Oichiro*

JAERI-Review 96-010, 40 Pages, 1996/08

JAERI-Review-96-010.pdf:1.14MB

no abstracts in English

Journal Articles

A Measurement method of fissioned-number in fuel for power calibration at critical assembly

Okazaki, Shuji

Radioisotopes, 45(10), p.63 - 64, 1996/00

no abstracts in English

JAEA Reports

None

; ; Shobu, Nobuhiro; ;

PNC-TN9700 95-001, 804 Pages, 1995/08

PNC-TN9700-95-001.pdf:30.97MB

no abstracts in English

Journal Articles

The nuclear fuel cycle safety engineering research facility (NUCEF) in JAERI-Tokai

Mineo, Hideaki; Yanagisawa, Hiroshi;

Hoshasen Kagaku, 0(60), p.47 - 50, 1995/00

no abstracts in English

Journal Articles

NUCEF project and its contribution to emerging fuel cycle back-end

Tonoike, Kotaro; Mineo, Hideaki; Takeshita, Isao; Tsujino, Takeshi

GLOBAL'93,Future Nuclear Systems: Emerging Fuel Cycles & Waste Disposal Options, 0, p.555 - 562, 1993/00

no abstracts in English

Journal Articles

Topics of NUCEF critical facilities

Yanagisawa, Hiroshi; Takeshita, Isao

Robutsuri No Kenkyu, (41), p.53 - 56, 1992/03

no abstracts in English

JAEA Reports

Measurements and calculations of neutron interaction effects of a two-coupled system in water

Miyoshi, Yoshinori; Suzaki, Takenori; ; Kobayashi, Iwao

JAERI-M 90-112, 45 Pages, 1990/07

JAERI-M-90-112.pdf:0.88MB

no abstracts in English

JAEA Reports

Critical Experiments Facility and Criticality Safety Programs at JAERI

; ; ; ; Miyoshi, Yoshinori;

JAERI-M 85-152, 17 Pages, 1985/10

JAERI-M-85-152.pdf:0.56MB

no abstracts in English

JAEA Reports

Program of Nuclear Criticality Safety Experiment at JAERI

; ; ;

JAERI-M 83-209, 11 Pages, 1983/11

JAERI-M-83-209.pdf:0.45MB

no abstracts in English

JAEA Reports

Experiment and Analysis of B$$_{4}$$C Simulateing Control Rod on FCA V-3 Assembly

; *; ; ; *; ;

JAERI-M 9055, 63 Pages, 1980/09

JAERI-M-9055.pdf:2.07MB

no abstracts in English

JAEA Reports

Journal Articles

On Heavy-Water Critical Assembly

Nippon Genshiryoku Gakkai-Shi, 11(5), p.301 - 305, 1969/00

no abstracts in English

23 (Records 1-20 displayed on this page)