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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) Nippon 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.

Journal Articles

Results of Current Fabrication Technology Developments and MOX Fuel Fabrication for JOYO MK-III Initial Load Fuel

Kayano, Masashi

Saikuru Kiko Giho, (21), p.41 - 47, 2003/00

In the plutonium fuel production facility, PFPF, MOX fuel fabrication technologies have been developed and demonstrated through MOX fuels fabrication for JOYO and MONJU since 1988. From 1995 to 2000, replacement, modification and repair work for process equipment had been carried out to improve performance of MOX pellet fabrication process in PFPF as scheduled shut-dawn maintenance. Because MOX fuel fabrication for JOYO MK-III initial load fuel was the first fuel fabrication after these major maintenance works, the performance of MOX pellet fabrication process in PFPF had been evaluated though this fuel fabrication. This MOX fuel fabrication was completed within the scheduled period and showed higher yield of product MOX pellets than before. Therefore, it was confirmed that performance of MOX pellet fabrication process in PFPF was improved by these maintenance work. Furthermore, quality assurance system for MOX fuel fabrication was strengthened by acquisition of ISO9001 certificate in

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

Oral presentation

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

Tazawa, Yuto; Hosogane, Tatsuya; Ishikawa, Fumitaka; Kayano, Masashi; Matsuyama, Kazutomi; Saito, Kosuke; Oishi, Shinichi*; Nakajima, Hiroshi*

no journal, , 

no abstracts in English

Oral presentation

Technical support from the IAEA for improvement of operator's analytical quality for Safeguards

Okazaki, Hiro; Sumi, Mika; Kayano, Masashi; Matsuyama, Kazutomi; Suzuki, Toru

no journal, , 

The Plutonium Fuel Development Center of Japan Atomic Energy Agency (JAEA-PFDC) received Japan's first plutonium in 1966 and commenced research to develop plutonium fuel as a key objective of the Japanese nuclear fuel cycle. Since then fundamental research with plutonium-bearing materials, and the development and fabrication of mixed uranium-plutonium oxide fuels, has been carried out. It is essential that the Operator's measurement quality be continually reviewed and improved for effective and efficient implementation of international Safeguards. In this context, and recognizing the excellent technical cooperation with IAEA measurement experts, JAEA-PFDC has continually worked to improve its measurement system. This paper will present examples of continual measurement improvement by JAEA-PFDC, and will show the benefit and effectiveness of technical support from IAEA towards this goal.

Oral presentation

Effective use of inspection samples as intercomparison samples for the quality control in safeguards analysis in Japan

Sumi, Mika; Okazaki, Hiro; Kayano, Masashi; Matsuyama, Kazutomi; Suzuki, Toru; Kuhn, E.*

no journal, , 

For the effective and efficient implementation of international Safeguards it is essential that the Operator's measurement system is maintained at a level of high quality and improved, as necessary. Besides the internal quality control, it is important to have elements of Quality Assurance (QA) in place, such as external intercomparison. However, there were no intercomparison programs with Pu samples available in Japan because of very few users and difficulties in the shipment. To cope with this situation, intercomparison by using actual safeguards samples containing Pu and U was started. Inspection samples are selected and prepared for shipment to the Safeguards laboratories together with other samples. Safeguards laboratories receive and analyze them as inspection samples as well as intercomparison without additional cost. The practicality and effective use of this DA intercomparison, which is operated since more than 20 years, will be explained.

Oral presentation

Development of liquid waste treatment method with insoluble tannins

Konno, Takahiro; Eda, Takashi; Kayano, Masashi

no journal, , 

Liquid waste containing radioactive materials (Pa and U) needs to remove those radioactive materials before being disposed of. The traditional method had a problem that the secondary wastes such as neutralized precipitates are generated, and it was necessary to develop a new treatment method that generates secondary wastes at the lowest amount possible. We've focused on the fact that the insoluble tannins are high adsorptive to TRU elements and U and are incinerable. JAEA-PFDC has developed the new liquid waste treatment method using the insoluble tannins. Through the beaker scale test, it was confirmed that insoluble tannins were effective for the liquid waste treatment. By the verification tests, we could remove radioactive materials without generation of neutralized precipitates.

Oral presentation

Effective use of inspection samples as intercomparison samples for the quality control in accountancy analysis

Okazaki, Hiro; Sumi, Mika; Kayano, Masashi; Matsuyama, Kazutomi; Suzuki, Toru; Kuhn, E.*

no journal, , 

For the effective and efficient implementation of international Safeguards, it is essential that the Operator's measurement system is maintained at a level of high quality and improved, as necessary. Besides the internal quality control, it is important to have elements of Quality Assurance (QA) in place, such as external intercomparison. However, there were no intercomparison programs with Plutonium samples available in Japan because of very few users and difficulties in the shipment of such samples from foreign laboratories. To cope with these difficult situations, intercomparison by using actual safeguards samples containing Plutonium and Uranium was started. Inspection samples are selected and prepared for shipment to the Safeguards laboratories together with other samples. Safeguards laboratories receive and analyze them as inspection samples as well as intercomparison without additional cost for analysis operation or sample transportation. The practicality and effective use of this DA intercomparison, which is operated since more than 20 years, will be explained.

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