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Journal Articles

Present Status of Monte Carlo Seminar for Sub-criticality Safety Analysis in Japan

Sakurai, Kiyoshi; Nojiri, Ichiro*

JAERI-Conf 2003-019, p.855 - 857, 2003/10

This paper provides overview of sub-criticality safety analysis seminar (July 2000-July 2003, JAERI, total 40 engineers from universities, research institutes and enterprises) for nuclear fuel cycle facility with the Monte Carlo method in Japan. MCNP-4C2 system (MS-DOS version) was installed in each note-type personal computer. Fundamental theory of reactor physics and Monte Carlo simulation including MCNP-4C manual was lectured. Effective neutron multiplication factor and neutron spectrum were calculated for JCO deposit tank, JNC uranium solution storage tank, JNC plutonium solution storage tank and JAERI TCA core. In the seminar, methodology of safety management for nuclear fuel cycle facility was discussed in order to prevent criticality accident.

Journal Articles

General description and operational experience of a dry storage facility for JRR-3 spent fuels in JAERI

Kusunoki, Tsuyoshi; Koda, Nobuyuki; Uchiyama, Junzo*

Dai-24-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu, p.149 - 156, 2003/00

A dry storage facility (DSF) was constructed in March 1982 to store the JRR-3 metallic natural uranium spent fuel elements those had been stayed under water in a core or a spent fuel pool for a long period (Maximum : about 20 years). The facility consists of a storage, an air circulation system, an auxiliary system and a control room. The storage is composed of the concrete shielding and 100 dry-wells. In each dry-well, a stainless steel made canister with the spent fuels is stored. The air circulation system has an air-inlet and outlet pipes, headers and air circulation blowers to circulate air in the system and maintain the pressure inside the dry-well below the atmosphere. This system also performs the role as radiation monitoring system. The facility is designed to satisfy safety requirements as a nuclear fuel facility, such as criticality safety, radiation shielding and earthquake performance. JAERI has successfully experienced the dry storage of 1798 spent fuel elements about for 20 years.

JAEA Reports

Criticality safety evaluation in Tokai reprocessing plant

Shirai, Nobutoshi; ; ; Shirozu, Hidetomo; Sudo, Toshiyuki; Hayashi, Shinichiro;

JNC TN8410 2000-006, 116 Pages, 2000/04

JNC-TN8410-2000-006.pdf:2.77MB

Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 "Criticality safety of single unit" in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units.

JAEA Reports

None

; ; ; ; ; ;

PNC TN8440 98-025, 111 Pages, 1998/07

PNC-TN8440-98-025.pdf:11.06MB

None

JAEA Reports

None

; Nakano, Tomoyuki; Miyazaki, Hitoshi;

PNC TN9420 94-015, 80 Pages, 1994/07

PNC-TN9420-94-015.pdf:2.92MB

None

Journal Articles

Research reactors and safeguards

Kaku Busshitsu Kanri Senta Nyusu, 21(5), p.7 - 9, 1992/05

no abstracts in English

JAEA Reports

None

; *; *; ; ; Enokido, Yuji

PNC TN9080 92-004, 55 Pages, 1992/03

PNC-TN9080-92-004.pdf:1.38MB

None

JAEA Reports

Research on $$gamma$$-irradiation effects on the Characteristics of Concrete

; *; *; *; ;

JAERI-M 85-097, 14 Pages, 1985/07

JAERI-M-85-097.pdf:1.12MB

no abstracts in English

JAEA Reports

Effect of $$gamma$$-ray Irradiation on The Properties of Concrete

; *; ; ; Araki, Kunio; ; ; ; *; *; et al.

JAERI-M 83-004, 38 Pages, 1983/02

JAERI-M-83-004.pdf:1.76MB

no abstracts in English

Journal Articles

Progress and status of the JRR-2 spent fuel storage facility

Sawai, Sadamu

Genshiryoku Kogyo, 11(6), p.49 - 55, 1965/00

no abstracts in English

Oral presentation

JAEA's R&D on volume reduction of contaminated soil generated by decontamination in Fukushima

Mitsui, Seiichiro; Sekiyama, Tomio; Kato, Mitsugu; Asazuma, Shinichiro; Kato, Hiroyasu*; Ueta, Shinzo*

no journal, , 

A huge volume of contaminated soils and wastes has been generated by off-site decontamination works in Fukushima and has been stored at temporary storage sites located near or at decontamination sites. The soils and wastes will be sequentially transferred to the Interim Storage Facility (ISF). According to a relevant law, the soils and wastes will be disposed at a final disposal site outside Fukushima within the next 30 years. The total volume of the contaminated soils which will be stored in the ISF is estimated to be up to 20 million cubic meters, thus reduction of its final disposal volume is vital to minimize various impacts of final disposal. In order to optimize final disposal outside Fukushima, the government will commence research and development on soil treatment techniques and use application of less-contaminated soil. As the one and only institution dedicated to the comprehensive R&D of nuclear energy-related technology in Japan, we will support the government efforts.

11 (Records 1-11 displayed on this page)
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