Annual report of Nuclear Emergency Assistance and Training Center (April 1, 2012 - March 31, 2013)

Sato, Takeshi; Muto, Shigeo; Okuno, Hiroshi; Katagiri, Hiromi; Akiyama, Kiyomitsu; Okamoto, Akiko; Koie, Masahiro; Ikeda, Takeshi; Nemotochi, Toshimasa; Saito, Toru; et al.

JAEA-Review 2013-046, 65 Pages, 2014/02

JAEA-Review-2013-046.pdf:11.18MB

When a nuclear emergency occurs in Japan, the Japan Atomic Energy Agency (JAEA) has the responsibility of providing technical support to the National government, local governments, police, fire stations and nuclear operators etc., because the JAEA has been designated as the Designated Public Institution under the Basic Act on Disaster Control Measures and the Act on Response to Armed Attack Situations, etc.. The Nuclear Emergency Assistance and Training Center (NEAT) of JAEA provides a comprehensive range of technical support activities to an Off-Site Center in case of a nuclear emergency. Specifically, NEAT gives technical advice and information, dispatches specialists as required, and supplies the National Government and local governments with emergency equipments and materials. NEAT provides various exercise and training courses concerning nuclear disaster prevention to those personnel taking an active part in emergency response organizations at normal times. The tasks of NEAT, with its past experiences as a designated public institution including the responses to TEPCO's Fukushima Accident, have been shifted to technical supports to the national government for strengthening its abilities to emergency responses; the NEAT therefore focused on maintenance and operation of its functions, and strengthening its response abilities in cooperation with the national government. This annual report summarized these activities of JAEA/NEAT in the fiscal year 2012.

Study on fluid mixing in a fuel subassembly of a fast reactor; Mixing phenomena with cross flow and applicability of subchannel analysis

Kawamata, Nobuhiro; Miyakoshi, Hiroyuki; Kamide, Hideki

JNC TN9400 2004-047, 99 Pages, 2004/08

JNC-TN9400-2004-047.pdf:8.02MB

Sodium experiments were carried out for mixing phenomena in a subassembly of fast reactor. A blockage was installed in a wire wrapped 37-pin subassembly in order to form cross flow around the blockage. Temperature distributions in the subassembly were measured under a condition that only one pin was heated. Investigation on mixing phenomena with the cross flow is useful to predict thermohydraulics in a deformed pin bundle of high burnup core. The subchannel analysis code, ASFRE, was applied to the experimental analyses. The ASFRE solves momentum equations in multi dimensions and has the distributed resistance model for a wire spacer.Following remarks were obtained:1).Measured axial temperature distributions showed that the sodium temperature decreased due to the core flow coming from the cold blockage side. Local peaks were found at the subchannels which have the wire spacer. 2).ASFRE simulated the temperature decreases due to the cross flow and axial temperature profiles were in good agreement with the measured data.3).The local peaks at wire positions were also simulated by ASFRE, however, the peak value was underestimated. ASFRE has high applicability to the mixing phenomena in a wire wrapped subassembly where the cross flow has significant role due to the change of flow area.4).Experimental database for the mixing phenomena with the cross flow were obtained for a subassembly of sodium cooled fast reactor.

Effect of argon ion irradiation on the mechanical properties of carbon materials

Oku, Tatsuo*; Kurumada, A.*; Nakata, M.*; Takeda, K.*; Kawamata, K.*; Arai, Taketoshi; Ishihara, Masahiro

Proceedings of 24th Biennial Conference on Carbon (CARBON '99), p.574 - 575, 1999/07

no abstracts in English

None

; Ishibashi, Takashi; ;

PNC TN8420 91-008, 16 Pages, 1991/03

PNC-TN8420-91-008.pdf:0.52MB

None

None

Koizumi, Masumichi; *; *; Nagai, Shuichiro; Furuya, Hirotaka

PNC TN841 76-23, 27 Pages, 1976/06

PNC-TN841-76-23.pdf:2.19MB

no abstracts in English

None

Koizumi, Masumichi; *; *; Furuya, Hirotaka

PNC TN841 73-26, 30 Pages, 1973/09

PNC-TN841-73-26.pdf:4.39MB

no abstracts in English

None

Koizumi, Masumichi; Komatsu, Junji*; Sasao, Nobuyuki*; Yokozawa, Naoki; *; Tachibana, Toshimichi; *; *

PNC TN841 72-39, 68 Pages, 1972/11

PNC-TN841-72-39.pdf:5.59MB

no abstracts in English

Physical and chemical properties of nuclear fuels; May,1971March, 1972

Koizumi, Masumichi; Komatsu, Junji*; Sasao, Nobuyuki*; *; Tachibana, Toshimichi; *; *

PNC TN843 72-02, 47 Pages, 1972/03

PNC-TN843-72-02.pdf:1.11MB

None

Development of advanced equipments for PIEs in JMTR-HL

Ito, Masayasu; Taguchi, Taketoshi; Yonekawa, Minoru; Kurosawa, Makoto; Kawamata, Kazuo; Sozawa, Shizuo; Ishihara, Masahiro

no journal, , 

JMTR-HL has been promoting the advancement of PIE meets future needs of irradiation, and has been constructing the position of basic research of nuclear energy for the purpose of realizing a research environment to support "Green Innovation " and "Life Innovation" such as measures for prolonged LWR that is a subject for study worldwide, development of Next Generation LWR, the development of radioisotopes manufacturing technology for medical use, and has been promoting the development of post-irradiation test facility that is selected by the Ministry of Education as "Cutting-Edge Research Infrastructure Projects" toward the achievement of a base for international R&D. This development has done TEM, FIB and XPS, etc. and have enabled the processing and the sample observation of irradiated material specimen of 30 MBq amount of radioactivity (in terms of cobalt).