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Journal Articles

Experience on return of research reactor spent fuels in Japan

Sagawa, Hisashi; Koda, Nobuyuki; Hanawa, Nobuhiro; Maruo, Takeshi; Miyazawa, Masataka; Unesaki, Hironobu*; Nakagome, Yoshihiro*

IAEA-TECDOC-1593, p.121 - 128, 2008/06

In Japan, 1,712 of Research Reactor Spent Nuclear fuels (RRSNFs) have been transported to the US successfully since the receipt in accordance with the foreign research reactor spent nuclear fuel acceptance policy started in 1996. Especially, Japan Atomic Energy Agency (JAEA) carried out shipment to the US of eight times and of 1,283 fuel elements in total. This paper describes experiences of RRSNF transportation to the US in Japan.

Journal Articles

Status of reduced enrichment program for research reactors in Japan

Nakagome, Yoshihiro*; Unesaki, Hironobu*; Sagawa, Hisashi

Proceedings of 27th International Meeting on Reduced Enrichment for Research and Test Reactors 2005 (RERTR 2005) (Internet), 10 Pages, 2006/00

no abstracts in English

Journal Articles

Status of reduced enrichment program for research reactors in Japan

Kinase, Masami; Sagawa, Hisashi; Nakagome, Yoshihiro*; Unesaki, Hironobu*

Proceedings of International Meeting on Reduced Enrichment for Research and Test Reactors 2006 (RERTR 2006) (Internet), 10 Pages, 2006/00

The reduced enrichment programs for the JRR-3M, JRR-4 and JMTR of Japan Atomic Energy Research Institute (JAERI) has been completed until 1999. The KUR of Kyoto University Research Reactor Institute (KURRI) has been partially completed and is still in progress under the Joint Study Program with Argonne National Laboratory (ANL). The JRR-3M using LEU silicide fuel elements has done a functional test by the Japanese Government in 2000, and the property of the reactor core was satisfied. JAERI established a "U-Mo fuel ad hoc committee" for feasibility study concerning future LEU fuel instead of the silicide fuel in 2001, and an installation of the U-Mo fuel was estimated from 2012, even the irradiation tests are carried out successfully. The U.S. Policy of Foreign Research Reactor Spent Nuclear Fuels is strongly expected to expand the policy until U-Mo fuel installed. The Japanese Government approved a cancellation of the KUHFR Project in February 1991, and in April 1994 the U.S. Government gave an approval to utilize HEU fuel in the KUR instead of the KUHFR. Therefore, the KUR will be operated with HEU fuel until March 2006, then the full core conversion with LEU fuel will be done. All KUR spent fuel elements will be sent to the U.S. by March 2008.

Journal Articles

RERTR-2004, International Meeting on Reduced Enrichment for Research and Test Reactors

Nakagome, Yoshihiro*; Shimizu, Kenichi

Kaku Busshitsu Kanri Senta Nyusu, 34(2), p.14 - 19, 2005/02

RERTR(Reduced Enrichment for Research and Test Reactors) for 2004 was held at IAEA in Vienna of Austria, An author and Professor Nakagome(Kyoto University) attended this internationalmeeting and the author presented "Status of Reduced Enrichment Program for Research Reactors in Japan" with Dr.Nakagome. JNMCC(Japan Nuclear Material Control Center) requested to present a report of 2004 RERTR international Meeting and related content for the author and Dr.Nakagome. the content of the report described the meeting content and related issue which related US FRR SNF(Foregin Reserach Reactors Spent Nuclear Fuels) Acceptance Program.

Journal Articles

Study on Tracking System for Radioactive Material Transport

; ; Nomura, Tamotsu; Nakagome, Yoshihiro*

Dai-14-Kai Hoshasei Busshitsu No Yuso Yoki To Yuso Ni Kansuru Kokusai Shimpojiumu, 0 Pages, 2004/00

The application of the fluoride volatility process in the reprocessing of fuel from the fast breeder reactor is regarded as one of the economical methods. Plutonium hexafluoride (PuF6), however, reacting with fluorine (F2) and plutonium dioxide (PuO2) as the raw material, is in an unstable condition and tends to remain as a solid compound in the process after decomposing into plutonium tetrafluoride (PuF4). Suitable conditions should be established for the practical use of this process. One of them is to enhance the stability of PuF6. The behaviour of plutonium fluorination and relevant chemical reactions were investigated by referring to sundry literature and by thermodynamic calculation. It was then compared with recent data from laboratory scale experiments for this paper. Results from the theoretical analysis agreed with experimental observation that PuF6 could be formed stably under a high temperature condition (approx.1000 K) with over supply of figher concentration of F2.

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