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Journal Articles

Development of Pu standard material preparation and characterization technique in Japan

Okazaki, Hiro; Shibano, Koya; Abe, Katsuo; Sumi, Mika; Kayano, Masashi; Kageyama, Tomio; Mason, P.*

Proceedings of INMM 57th Annual Meeting (Internet), 7 Pages, 2016/07

The reference materials used for accountancy analysis by IDMS, referred to as LSD spikes allows to obtain accurate measurement results for a variety of nuclear materials under potentially difficult handling or measurement conditions. Because of expected difficulties in a stably long term supply of plutonium reference materials, which are the main source of plutonium for LSD spikes preparation, the JAEA's PFDC decided to evaluate the possibility of using domestically available MOX powders as a plutonium source material for LSD spikes. Therefore, PFDC started to separate, purify and characterize plutonium in MOX powders for plutonium reference materials (MOX-Pu) preparation that are suitable for source of LSD spikes in cooperation with the US DOE's NBL. The detailed preparation procedure of the latest MOX-Pu standard material and results of intercomparison for verification are presented.

Journal Articles

Approaches to characterization of nuclear material for establishment of nuclear forensics

Okazaki, Hiro; Sumi, Mika; Sato, Mitsuhiro; Kayano, Masashi; Kageyama, Tomio; Martinez, P.*; Xu, N.*; Thomas, M.*; Porterfield, D.*; Colletti, L.*; et al.

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-35-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2015/01

The quality control section of Plutonium Fuel Development Center (PFDC) in Japan Atomic Energy Agency has been analyzing isotopic compositions and content of plutonium and uranium as well as impurity and physics of nuclear materials in the process of MOX fuel fabrication for accountancy purpose as well as process control purposes. These analytical techniques are also effective for nuclear forensics to identify the source, history, and route of the material by determining a composition and chemical property of it. Therefore, PFDC cooperates with Los Alamos National Laboratory which has broad experience and established measurement skill for nuclear forensics, and evaluates the each method, procedure, and analytical data toward R&D of characterizing a nuclear fuel for forensics purposes. This paper describes the approaches to develop characterization techniques of nuclear fuel for nuclear forensic purpose at PFDC.

Oral presentation

Visualization of current density distributions with neutron spin interferometer

Hayashida, Hirotoshi; Yamazaki, Dai; Ebisawa, Toru*; Maruyama, Ryuji; Soyama, Kazuhiko; Takenaka, Nobuyuki*; Kageyama, Masashi*; Tasaki, Seiji*; Hino, Masahiro*; Kawabata, Yuji*; et al.

no journal, , 

no abstracts in English

Oral presentation

Demonstration of magnetic imaging with neutron spin interferometer

Hayashida, Hirotoshi; Yamazaki, Dai; Ebisawa, Toru*; Maruyama, Ryuji; Soyama, Kazuhiko; Iikura, Hiroshi; Yasuda, Ryo; Sakai, Takuro; Matsubayashi, Masahito; Takenaka, Nobuyuki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Visualization of magnetic field with Neutron Spin Interferometer

Hayashida, Hirotoshi; Yamazaki, Dai; Ebisawa, Toru*; Maruyama, Ryuji; Soyama, Kazuhiko; Iikura, Hiroshi; Yasuda, Ryo; Sakai, Takuro; Matsubayashi, Masahito; Takenaka, Nobuyuki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Visualization of magnetic field with neutron spin interferometer

Hayashida, Hirotoshi; Yamazaki, Dai; Ebisawa, Toru*; Maruyama, Ryuji; Soyama, Kazuhiko; Iikura, Hiroshi; Yasuda, Ryo; Sakai, Takuro; Matsubayashi, Masahito; Takenaka, Nobuyuki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of automatic detection and measurement system for the Pu spot in the MOX fuel pellet

Hosogane, Tatsuya; Ishikawa, Fumitaka; Kageyama, Tomio; Kayano, Masashi; Kodaira, Satoshi*; Kurano, Mieko*

no journal, , 

For the safe design of MOX fuel, plutonium (Pu) spot analysis is an important control point, thus maximum diameter and Pu content of the Pu spot is defined as MOX fuel specification. Diameter and Pu content of the Pu spot has been analyzed by detecting Pu spot from pictures taken by alpha-autoradiography using commercial imaging analysis software and measure its diameter and content by hand work. Because this method requires a lot of work, automatic detection and measurement system for the Pu spot diameter and Pu content was developed to save workload.

Oral presentation

Achievement and future task of Pu standard material preparation technique in Japan

Shibano, Koya; Okazaki, Hiro; Sumi, Mika; Kayano, Masashi; Matsuyama, Kazutomi; Kageyama, Tomio; Fujiwara, Hideki*; Furuta, Koya*; Yamaguchi, Kazuya*; Saito, Shingo*

no journal, , 

no abstracts in English

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