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Journal Articles

On a fast reactor cycle scheme that incorporates a thoria-based minor actinide-containing cermet fuel

Osaka, Masahiko; Takano, Sho*; Yamane, Yoshihiro*; Misawa, Tsuyoshi*

Progress in Nuclear Energy, 50(2-6), p.212 - 218, 2008/03

 Times Cited Count:6 Percentile:57.24(Nuclear Science & Technology)

Concept of fast reactor cycle scheme that incorporates a thoria-based minor actinide-containing cermet fuel is given. The present cermet fuel consists of oxide solid solution of Th and minor actinides and Mo inert matrix. It has been proposed as a high-performance device that can enhance minor actinide transmutation in the fast reactor cycle. It is used in an independent small cycle, whereby dedicated cycle process are adopted. Two-steps process for reprocessing of the present cermet fuel was proposed; it consists of pre-removal of Mo-inert matrix and actinide recovery. A preliminary test for pre-removal of Mo-inert matrix using surrogate cermet fuel was carried out. It was done by dissolution in nitric acid at room temperature. Results showed that Mo-inert matrix was largely dissolved, while oxide remained. Burnup characteristics of a fast reactor core loaded with the cermet fuel were investigated by using neutronic calculation codes. It was revealed that a heterogeneous composition of Mo-inert matrix in inner and outer cores could lead to effective transmutation and flattened power density. It was concluded that the present cermet fuel is potentially a promising one as a high-performance transmutation device for the fast reactor.

Journal Articles

Retrospective estimation of the spatial dose distribution and the number of fissions in criticality accident using area dosimeters

Sono, Hiroki; Ono, Akio; Kojima, Takuji; Yamane, Yoshihiro*

Journal of Nuclear Science and Technology, 44(1), p.43 - 53, 2007/01

 Times Cited Count:2 Percentile:78.08(Nuclear Science & Technology)

A practical method is proposed for retrospective estimation of the spatial dose distribution and the number of fissions in a typical criticality accident. In this method, two kinds of low-fading and tissue-equivalent dosimeters are used as area dosimeters: an alanine dosimeter and a thermoluminescence dosimeter made of enriched lithium tetra borate. The procedure of the method consists of four parts: (1) dosimetry using area dosimeters (2) search for the center of the radiation source, (3) estimation of the spatial dose distribution, and (4) estimation of the number of fissions. Dosimetry of criticality accident situations simulated at the TRACY facility demonstrates the practicability of the method. Although a post-hoc analysis in principle, this method gives useful information on the magnitude and hazard level of the accident to determine the strategy of radiation emergency medicine and other post-accident measures if the area dosimeters are retrieved immediately after the accident.

Journal Articles

A Novel concept for americium-containing target for use in fast reactors

Osaka, Masahiko; Koi, Mamoru; Takano, Sho*; Yamane, Yoshihiro*; Misawa, Tsuyoshi*

Journal of Nuclear Science and Technology, 43(4), p.367 - 374, 2006/04

 Times Cited Count:12 Percentile:29.56(Nuclear Science & Technology)

The low oxygen potential target, which consist of (Th,Am)Ox dispersed in Mo, as a high performance Am-containing target for fast reactors is proposed. Effects of Mo isotopic ratio on the core characteristics are evaluated with various Mos having different isotopic composition.

Journal Articles

Assessment of human body surface and internal dose estimations in criticality accidents based on experimental and computational simulations

Sono, Hiroki; Ono, Akio*; Kojima, Takuji; Takahashi, Fumiaki; Yamane, Yoshihiro*

Journal of Nuclear Science and Technology, 43(3), p.276 - 284, 2006/03

 Times Cited Count:1 Percentile:88.23(Nuclear Science & Technology)

For a study on the applicability of a personal dosimetry method to criticality accident dosimetry, an assessment of the human body surface and internal dose estimations was performed by experimental and computational simulations. The experimental simulation was carried out in a criticality accident situation at the TRACY facility. The neutron and $$gamma$$-ray absorbed doses in muscle tissue were separately estimated by a dosimeter set of an alanine dosimeter and a thermoluminescence dosimeter made of enriched lithium tetra borate with a phantom. The computational simulation was conducted with a Monte Carlo code taking account of dose components of neutrons, prompt $$gamma$$-rays and delayed $$gamma$$-rays. The computational simulation was ascertained to be valid by comparison between the calculated dose distributions in the phantom and the measured ones. The assessment based on the experimental and computational simulations confirmed that the personal dosimetry using the dosimeter set provided a first estimation of the body surface and internal doses with precision.

Journal Articles

A Note on the diven factor in fast systems

Okajima, Shigeaki; Yamane, Yoshihiro*; Takemoto, Yoshinari*; Sakurai, Takeshi

Journal of Nuclear Science and Technology, 37(8), p.720 - 723, 2000/08

no abstracts in English

Journal Articles

Benchmark experiments of effective delayed neutron fraction $$beta$$$$_{eff}$$ in JAERI-FCA

Sakurai, Takeshi; Okajima, Shigeaki; ; Osugi, Toshitaka; M.Martini*; P.Chaussonnet*; H.Philibert*; I.P.Matveenko*; S.P.Belov*; V.A.Doulin*; et al.

Proc. of Int. Conf. on Physics of Nucl. Science and Technol., 1, p.182 - 189, 1998/00

no abstracts in English

Journal Articles

Present status of nuclear criticality safety research; Highlights of ICNC'95, the 5th International Conference on Nuclear Criticality Safety

*; *; Miyoshi, Yoshinori; Suzaki, Takenori; Okuno, Hiroshi; Nomura, Yasushi; Mitake, Susumu*; ; Tonoike, Kotaro; *; et al.

Nippon Genshiryoku Gakkai-Shi, 38(4), p.262 - 271, 1996/00

no abstracts in English

JAEA Reports

Calculation of fine neutron spectrum in irradiation holes in fuel region of JRR-3M

; Nakano, Yoshihiro; Yamane, Yoshihiro*; *;

JAERI-Research 95-059, 83 Pages, 1995/09

JAERI-Research-95-059.pdf:2.24MB

no abstracts in English

Journal Articles

Present status of nuclear criticality safety research; highlights of International Conference on Nuclear Criticality Safety(ICNC-91)

*; Yamane, Yoshihiro*; Kobayashi, Iwao; Tachimori, Shoichi; ; Miyoshi, Yoshinori; Okuno, Hiroshi; Nakajima, Ken; Mitake, Susumu*; *; et al.

Nippon Genshiryoku Gakkai-Shi, 34(4), p.311 - 319, 1992/04

 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Development of reactivity feedback effect measurement techniques under sub-critical condition in fast reactor, 1-5; FCA experimental plan

Fukushima, Masahiro; Okajima, Shigeaki; Kitamura, Yasunori; Ando, Masaki; Yamane, Tsuyoshi; Mori, Takamasa; Nishi, Hiroshi; Yamane, Yoshihiro*; Kanemoto, Shigeru*

no journal, , 

no abstracts in English

Oral presentation

Development of reactivity feedback effect measurement techniques under sub-critical condition in fast reactor, 1-1; Purpose and program

Okajima, Shigeaki; Nishi, Hiroshi; Yamane, Yoshihiro*; Kanemoto, Shigeru*; Yamane, Tsuyoshi; Mori, Takamasa; Kitamura, Yasunori; Fukushima, Masahiro; Kitano, Akihiro; Ando, Masaki; et al.

no journal, , 

The program was planned and has been carried out to develop of the reactivity feedback effect measurement techniques under sub-critical condition in the start-up experiment for fast reactors. The program includes the demonstration of the developed technique in fast critical assembly (FCA) and the proposal of the appropriate measurement system based on the results. The background and the purposes of the program and the outline of development subjects are presented.

Oral presentation

Development of reactivity feedback effect measurement techniques under sub-critical condition in fast reactor, 1-2; Development of acquisition system with high time-resolution for long time-series data

Kitamura, Yasunori; Yamane, Yoshihiro*; Okajima, Shigeaki; Fukushima, Masahiro; Ando, Masaki; Yamane, Tsuyoshi

no journal, , 

no abstracts in English

Oral presentation

Fundamental study of inert matrix fuels adaptable to a fast reactor cycle system, 1; Concept

Osaka, Masahiko; Miwa, Shuhei; Kurosaki, Ken*; Yamanaka, Shinsuke*; Uno, Masayoshi*; Yamane, Yoshihiro*; Mimura, Hitoshi*; Yano, Toyohiko*

no journal, , 

Inert matrix fuel concept that is adaptable to the fast reactor cycle system was proposed. The concept has unique characteristics of a flexible management of minor actinides and effective utilization of beneficial materials in the nuclear cycle.

Oral presentation

Isolation of UVB-torelant/sensitive rice plants and analysis of the mutated genes

Takano, Nao*; Yamamoto, Mitsuru*; Takahashi, Yuko*; Teranishi, Mika*; Sakamoto, Ayako; Hase, Yoshihiro; Tanaka, Atsushi; Wu, J.*; Matsumoto, Takashi*; Toki, Seiichi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of reactivity feedback effect measurement techniques under sub-critical condition in fast reactor, 2-3; FCA experiment; Modified source multiplication method

Fukushima, Masahiro; Kitamura, Yasunori; Ando, Masaki; Okajima, Shigeaki; Yamane, Tsuyoshi; Yamane, Yoshihiro*

no journal, , 

no abstracts in English

Oral presentation

Development of reactivity feedback effect measurement techniques under sub-critical condition in fast reactor, 2-4; FCA experimen; Reactor noise method

Kitamura, Yasunori; Fukushima, Masahiro; Ando, Masaki; Okajima, Shigeaki; Yamane, Tsuyoshi; Yamane, Yoshihiro*

no journal, , 

no abstracts in English

Oral presentation

Development of reactivity feedback effect measurement techniques under sub-critical condition in fast reactor, 2-1; Skelton of program

Okajima, Shigeaki; Nishi, Hiroshi; Kanemoto, Shigeru*; Yamane, Yoshihiro*; Fukushima, Masahiro; Kitamura, Yasunori; Kitano, Akihiro; Suzuki, Takayuki; Ando, Masaki; Yamane, Tsuyoshi

no journal, , 

no abstracts in English

18 (Records 1-18 displayed on this page)
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