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Journal Articles

Investigation of irradiation conditions for recurrent breast cancer in JRR-4

Horiguchi, Hironori; Nakamura, Takemi; Kumada, Hiroaki*; Yanagie, Hironobu*; Suzuki, Minoru*; Sagawa, Hisashi

Proceedings of 14th International Congress on Neutron Capture Therapy (ICNCT-14) (CD-ROM), p.234 - 237, 2010/10

Recurrent breast cancer has been considered the application for boron neutron capture therapy using the JRR-4. The investigation of irradiation conditions for the recurrent breast cancer was performed by simulation with the JCDS. We performed the preliminary dosimetry of the model to verify the efficient irradiation conditions such as the neutron energy modes and multiple field technique. From the result, when the 30 Gy-Eq dose as minimum dose was delivered to the cancers, comparable dose distribution was delivered at the healthy tissues by both a one-port irradiation from anterior direction and a two-port irradiation from tangential direction. We revealed that the two-port irradiation was not valid to reduce the healthy tissues dose due to the isotopic scattering of neutrons in the body. We concluded that the optimal irradiation condition was the one-port irradiation with thermal neutron beam mode in terms of less healthy tissues dose and shorter irradiation time.

Journal Articles

Conceptual study for the hollow core of a research reactor

Komeda, Masao; Arai, Masaji; Sagawa, Hisashi; Kusunoki, Tsuyoshi

Proceedings of 12th International Group on Research Reactors (12th IGORR) (USB Flash Drive), 9 Pages, 2009/10

JAEA Reports

Investigation of the irradiation method for 12 inch NTD silicon in JRR-3 (Contract research)

Komeda, Masao; Yamamoto, Kazuyoshi; Yagi, Masahiro; Sagawa, Hisashi

JAEA-Technology 2008-064, 77 Pages, 2008/10

JAEA-Technology-2008-064.pdf:6.7MB

We investigated the irradiation method to irradiate 12 inch NTD silicon uniformly in JRR-3, where 6 inch NTD silicon is being irradiated at present, by using MVP of the Monte Carlo calculation code. In the case of irradiating 12 inch NTD silicon, the deviation of the doping distribution in the radial direction becomes 1.17 by the same irradiation method of 6 inch NTD silicon. Therefore the thermal neutron filter was introduced for uniform doping (the deviation is less than 1.10) in the radial direction and the effect was analyzed. As the result, it was indicated that the deviation of the doping distribution in the radial direction became less than 1.1 by using the neutron filter, which was made from aluminum alloy of 2 mm thickness including natural boron of 1%.

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.

JAEA Reports

Low temperature tritium release experiment from lithium titanete breeder material

Tsuchiya, Kunihiko; Kawamura, Hiroshi; Nakamichi, Masaru*; Sagawa, Hisashi

JAERI-Tech 2005-013, 56 Pages, 2005/03

JAERI-Tech-2005-013.pdf:6.4MB

no abstracts in English

Journal Articles

Irradiation effects on magnetic probes made of mineral insulated cable

Nishitani, Takeo; Shikama, Tatsuo*; Fukao, M.*; Matsuo, H.*; Snider, R.*; Broesch, J.*; Sagawa, Hisashi; Kawamura, Hiroshi; Kasai, Satoshi

Fusion Engineering and Design, 51-52(Part.B), p.153 - 158, 2000/11

 Times Cited Count:9 Percentile:43.58(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Integrated experiment of blanket in-pile mockup with Li$$_{2}$$TiO$$_{3}$$ pebbles

Tsuchiya, Kunihiko; Nakamichi, Masaru; Nagao, Yoshiharu; Fujita, J.*; Sagawa, Hisashi; Tanaka, Satoru*; Kawamura, Hiroshi

Fusion Engineering and Design, 51-52, p.887 - 892, 2000/11

 Times Cited Count:9 Percentile:43.58(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Neutron irradiation test of optical components for fusion reactor

Ishitsuka, Etsuo; Sagawa, Hisashi; Nagashima, Akira; Sugie, Tatsuo; Nishitani, Takeo; Yamamoto, Shin; Kawamura, Hiroshi

Effects of Radiation on Materials (ASTM STP 1366), p.1176 - 1185, 2000/00

no abstracts in English

Journal Articles

Improvement of irradiation facilities performance in JMTR

Kanno, Masaru; ; ; Sagawa, Hisashi;

JAERI-Conf 99-006, p.264 - 269, 1999/08

no abstracts in English

JAEA Reports

Irradiation effects on plasma diagnostic components

Nishitani, Takeo; *; Ikeda, Yujiro; Ishitsuka, Etsuo; Kakuta, Tsunemi; Kasai, Satoshi; Kawamura, Hiroshi; Morita, Yosuke; Nagashima, Akira; Nakamichi, Masaru; et al.

JAERI-Research 98-053, 105 Pages, 1998/10

JAERI-Research-98-053.pdf:4.78MB

no abstracts in English

Journal Articles

Japanese contribution to ITER task of irradiation tests on diagnostics components

Nishitani, Takeo; Ishitsuka, Etsuo; Kakuta, Tsunemi; Sagawa, Hisashi; Oyama, Yukio; *; Sugie, Tatsuo; Noda, Kenji; Kawamura, Hiroshi; Kasai, Satoshi

Fusion Engineering and Design, 42, p.443 - 448, 1998/00

 Times Cited Count:22 Percentile:15.18(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Tritium release behavior from lithium titanate pebbles at low irradiation temperature

Kawamura, Hiroshi; Tsuchiya, Kunihiko; Nakamichi, Masaru; Fujita, J.*; Sagawa, Hisashi; Nagao, Yoshiharu; Y.Gohar*; ; Saito, Takashi; ; et al.

Fusion Technology 1998, 2, p.1289 - 1292, 1998/00

no abstracts in English

Journal Articles

Characterization of self-powered neutron detector at high temperature under neutron irradiation

Nakamichi, Masaru; *; Kawamura, Hiroshi; Sagawa, Hisashi; Nakazawa, Masaharu*

Fusion Technology 1996, 0, p.1591 - 1594, 1997/00

no abstracts in English

Journal Articles

Design study of in-pile blanket mockup simulated neutron pulse operation of fusion reactor

Nakamichi, Masaru; Sagawa, Hisashi; Yamaguchi, Katsuyoshi*; *; Kawamura, Hiroshi

Fusion Technology 1996, 0, p.1351 - 1354, 1997/00

no abstracts in English

JAEA Reports

Irradiation tests on diagnostics components for ITER in 1995

Nishitani, Takeo; *; Ikeda, Yujiro; Ishitsuka, Etsuo; Kakuta, Tsunemi; Kasai, Satoshi; Kawamura, Hiroshi; Maekawa, Fujio; Morita, Yosuke; Nagashima, Akira; et al.

JAERI-Tech 96-040, 22 Pages, 1996/10

JAERI-Tech-96-040.pdf:0.85MB

no abstracts in English

Journal Articles

Status of fusion blanket irradiation study in JAERI

Kawamura, Hiroshi; Sagawa, Hisashi; Ishitsuka, Etsuo; Tsuchiya, Kunihiko; Nakamichi, Masaru

Proc. of Int. Tritium Workshop on Present Status and Prospect of Tritium-Material Interaction Studies, 0(0), p.47 - 52, 1996/07

no abstracts in English

Journal Articles

Status of fusion blanket irradiation in JAERI

Kawamura, Hiroshi; Sagawa, Hisashi; Ishitsuka, Etsuo; Tsuchiya, Kunihiko; Nakamichi, Masaru; Saito, Shigeru

Proc. of 5th Int. Workshop on Ceramic Breeder Blanket Interaction, 0, p.87 - 96, 1996/00

no abstracts in English

Journal Articles

Characteristics of pebble packing and evaluation of sweep gas pressure drop into the in-pile mock-up fusion blanket

Ishitsuka, Etsuo; Nakamichi, Masaru; Kawamura, Hiroshi; Sagawa, Hisashi; *; *; Saito, Minoru

Journal of Nuclear Materials, 212-215, p.881 - 884, 1994/00

 Times Cited Count:2 Percentile:70.97(Materials Science, Multidisciplinary)

no abstracts in English

47 (Records 1-20 displayed on this page)