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Journal Articles

Dataset of TLD badge response and hair activation for criticality accident neutron dosimetry

Tsujimura, Norio; Takahashi, Fumiaki; Takada, Chie

Progress in Nuclear Science and Technology (Internet), 6, p.148 - 151, 2019/01

Journal Articles

Investigation of a model to evaluate the pyrolysis properties of zinc stearate

Abe, Hitoshi; Tashiro, Shinsuke; Miyoshi, Yoshinori

Nippon Genshiryoku Gakkai Wabun Rombunshi, 6(1), p.10 - 21, 2007/03

In MOX fuel fabrication facility, zinc stearate will be added into the MOX powder as addition material. If the material is added in large excess by miss operation, criticality characteristics of the MOX fuel would be influenced because it has neutron moderation effect. If criticality condition should be induced by the excess addition, physical variations, such as melting and pyrolysis of the material, must be caused by the fission energy and dynamic characteristics of the MOX fuel must be affected. To contribute quantitative evaluation of the dynamic characteristics, thermal properties data such as exo/endothermic calorific values, reaction rates, etc. with the respective physical variations and release behavior of pyrolysis gas were measured. It was found the exo/endothermic behavior with rinsing temperature of the material could be divided into six regions and rapid pressure rise caused by the pyrolysis reaction over about 400 $$^{circ}$$C. Furthermore, on the basis of the results, evaluation model for the thermal properties under the criticality condition was also investigated.

Journal Articles

Validation of simplified evaluation models for first peak power, energy, and total fissions of a criticality accident in a nuclear fuel processing facility by TRACY experiments

Nomura, Yasushi*; Okuno, Hiroshi; Miyoshi, Yoshinori

Nuclear Technology, 148(3), p.235 - 243, 2004/12

 Times Cited Count:3 Percentile:73(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Power profile evaluation of the JCO precipitation vessel based on the record of the $$gamma$$-ray monitor

Tonoike, Kotaro; Nakamura, Takemi*; Yamane, Yuichi; Miyoshi, Yoshinori

Nuclear Technology, 143(3), p.364 - 372, 2003/09

 Times Cited Count:2 Percentile:78.71(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Simplified estimation of criticality accident of MOX powder fuel

Miyoshi, Yoshinori; Yamamoto, Toshihiro; Nakajima, Ken

JAERI-Research 2002-002, 30 Pages, 2003/03

JAERI-Research-2002-002.pdf:1.42MB

no abstracts in English

Journal Articles

The Inhabitants' reaction after contact with disaster information at the JCO criticality accident

Umemoto, Michitaka; Ishigami, Tsutomu; Kobayashi, Kensuke

Chiiki Anzen Gakkai Rombunshu, 4, p.231 - 240, 2002/11

no abstracts in English

Journal Articles

Mechanisms of positive temperature reactivity coefficients of dilute plutonium solutions

Yamamoto, Toshihiro; Miyoshi, Yoshinori

Nuclear Science and Engineering, 142(3), p.305 - 314, 2002/11

 Times Cited Count:1 Percentile:88.46(Nuclear Science & Technology)

Mechanisms of a positive temperature reactivity coefficient that occurs in a dilute plutonium solution are investigated based on the perturbation theory and the four-factor formula. The temperature coefficient of a solution fuel is positive if the adjoint flux or ηf between 0.05eV and 0.2eV increases with neutron energy. As compared to Pu-239, Pu-241 has a tendency to make the temperature coefficient of a plutonium solution. As Pu-241 in a plutonium solution decays into Am-241 with time, the temperature coefficient becomes more positive. Since the capture cross sections of most neutron absorbers such as boron and gadolinium decreases with increasing neutron energy, soluble absorbers make the temperature coefficient positive for higher concentration plutonium solution. Cadmium and samarium solved in a dilute plutonium solution exceptionally can keep the temperature coefficient. A fixed neutron absorber generally makes the temperature coefficient negative regardless of the property of absorber materials.

Journal Articles

Determination of $$gamma$$-ray exposure rate from short-lived fission products under criticality accident conditions

Yanagisawa, Hiroshi; Ono, Akio; Aizawa, Eiju

Journal of Nuclear Science and Technology, 39(5), p.499 - 505, 2002/05

 Times Cited Count:4 Percentile:67.14(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Simulation tests for thermal characteristics of JCO precipitation vessel using a mock-up device

Watanabe, Shoichi; Miyoshi, Yoshinori; Yamane, Yuichi

JAERI-Tech 2002-043, 93 Pages, 2002/03

JAERI-Tech-2002-043.pdf:6.74MB

no abstracts in English

JAEA Reports

TRACY transient experiment databook, 3; Ramp feed experiment

Nakajima, Ken; Yamane, Yuichi; Ogawa, Kazuhiko; Aizawa, Eiju; Yanagisawa, Hiroshi; Miyoshi, Yoshinori

JAERI-Data/Code 2002-007, 123 Pages, 2002/03

JAERI-Data-Code-2002-007.pdf:4.34MB

no abstracts in English

JAEA Reports

TRACY transient experiment databook, 2; Ramp withdrawal experiment

Nakajima, Ken; Yamane, Yuichi; Ogawa, Kazuhiko; Aizawa, Eiju; Yanagisawa, Hiroshi; Miyoshi, Yoshinori

JAERI-Data/Code 2002-006, 176 Pages, 2002/03

JAERI-Data-Code-2002-006.pdf:6.33MB

no abstracts in English

JAEA Reports

TRACY transient experiment databook, 1; Pulse withdrawal experiment

Nakajima, Ken; Yamane, Yuichi; Ogawa, Kazuhiko; Aizawa, Eiju; Yanagisawa, Hiroshi; Miyoshi, Yoshinori

JAERI-Data/Code 2002-005, 158 Pages, 2002/03

JAERI-Data-Code-2002-005.pdf:6.55MB

no abstracts in English

JAEA Reports

A Kinetics code for criticality accident analysis of fissile solution systems: AGNES2

Nakajima, Ken; Yamane, Yuichi; Miyoshi, Yoshinori

JAERI-Data/Code 2002-004, 42 Pages, 2002/03

JAERI-Data-Code-2002-004.pdf:1.51MB

no abstracts in English

JAEA Reports

JCO criticality accident termination operation

Kanamori, Masashi

JNC-TN8440 2001-018, 50 Pages, 2001/12

JNC-TN8440-2001-018.pdf:1.31MB

On September 30 at around 10:35 AM, criticality accident occurred at the JCO's conversion building in Tokai-mura. Since criticality accident had not been anticipated, neither devices for termination of criticality accident nor neutron detectors were available. Immediately after the information of the accident, our emergency staff(Japan Nuclear cycle development institute staff) went to JCO site, to measure the intensity of neutrons and gammas. There were four main tasks, first one was to measure the radiation intensity, second one was to terminate the criticality accident, third one is to alert the residents surrounding the JCO site, fourth one is to evacuate the employees in the site. These tasks were successfully performed until October 1. This paper describes about how these operations were performed by the relevant staffs.

Journal Articles

The 1th and 2th Seminar on Subcriticality Safety with Monte Carlo Method on Nuclear Fuel Cycle Facility

Sakurai, Kiyoshi

Nippon Genshiryoku Gakkai-Shi, 43(11), P. 1113, 2001/11

no abstracts in English

Journal Articles

Source term on release behavior of radioactive materials from fuel solution under simulated nuclear criticality accident

Abe, Hitoshi; Tashiro, Shinsuke; Koike, Tadao; Okagawa, Seigo; Uchiyama, Gunzo

Proceedings of the 2001 Topical Meeting on Practical Implementation of Nuclear Criticality Safety (CD-ROM), 8 Pages, 2001/11

no abstracts in English

Journal Articles

Outline of the emergency response activity of JAERI Tokai research establishment

Yamahara, Takeshi

Dai-26, 27-Kai NS Netto Anzen Kyaraban Koenroku, p.1 - 30, 2001/10

no abstracts in English

Journal Articles

Measurement of neutron and $$gamma$$-ray absorbed doses under criticality accident conditions at TRACY using tissue-equivalent dosimeters

Sono, Hiroki; Yanagisawa, Hiroshi; Ono, Akio; Kojima, Takuji; Soramasu, Noboru*

Nuclear Science and Engineering, 139(2), p.209 - 220, 2001/10

 Times Cited Count:7 Percentile:46.86(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of dose distribution and neutron spectra in JCO critical accident by shielding calculations

Sakamoto, Yukio

KEK Proceedings 2001-14, p.236 - 242, 2001/06

no abstracts in English

JAEA Reports

81 (Records 1-20 displayed on this page)