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JAEA Reports

Development of the JAERI Computational Dosimetry System (JCDS) for boron neutron capture therapy (Cooperative research)

Kumada, Hiroaki; Yamamoto, Kazuyoshi; Torii, Yoshiya; Matsumura, Akira*; Yamamoto, Tetsuya*; Nose, Tadao*; Nakagawa, Yoshinobu*; Kageji, Teruyoshi*; Uchiyama, Junzo

JAERI-Tech 2003-002, 49 Pages, 2003/03

JAERI-Tech-2003-002.pdf:5.22MB

no abstracts in English

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

Production of a faithful realistic phantom to human head and thermal neutron flux measurement on the brain surface (Cooperative research)

Yamamoto, Kazuyoshi; Kumada, Hiroaki; Kishi, Toshiaki; Torii, Yoshiya; Endo, Kiyoshi*; Yamamoto, Tetsuya*; Matsumura, Akira*; Uchiyama, Junzo; Nose, Tadao*

JAERI-Tech 2002-092, 23 Pages, 2002/12

JAERI-Tech-2002-092.pdf:5.22MB

Thermal neutron flux is determined using the gold wires in current BNCT irradiation, so evaluation of arbitrary points after the irradiation is limited in the quantity of these detectors. In order to make up for the weakness, dose estimation of a patient is simulated by a computational dose calculation supporting system. In another way without computer simulation, a medical irradiation condition can be replicate experimentally using of realistic phantom which was produced from CT images by rapid prototyping technique. This phantom was irradiated at a same JRR-4 neutron beam as clinical irradiation condition of the patient and the thermal neutron distribution on the brain surface was measured in detail. This experimental evaluation technique using a realistic phantom is applicable to in vitro cell irradiation experiments for radiation biological effects as well as in-phantom experiments for dosimetry under the nearly medical irradiation condition of patient.

Journal Articles

Situation of test and research reactors' spent fuels

; Uchiyama, Junzo; Sato, Hiroshi

Dai-17-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu, 0, p.1 - 4, 1996/00

no abstracts in English

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