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Journal Articles

Study on heterogeneous minor actinide loading fast reactor core concepts with improved safety

Ohgama, Kazuya; Oki, Shigeo; Kitada, Takanori*; Takeda, Toshikazu*

Proceedings of 21st Pacific Basin Nuclear Conference (PBNC 2018) (USB Flash Drive), p.942 - 947, 2018/09

Journal Articles

R&D of the heat measurement method for accurate determination of amount of minor actinides samples for accuracy improvement of neutron nuclear data

Nakao, Taro; Nakamura, Shoji; Terada, Kazushi; Kimura, Atsushi; Harada, Hideo; Igashira, Masayuki*; Katabuchi, Tatsuya*; Hori, Junichi*

JAEA-Conf 2015-003, p.303 - 306, 2016/03

In spite of that the precise information of the total amount of the measurement sample is required for the neutron capture cross-section determination, it is not always performed in sufficient accuracy. Therefore, it is necessary to determine the absolute amount of samples accurately with non-destructively. This presentation will report on the future plan about the heat deposit measurement from minor actinides samples in order to determine the absolute amount of samples non-destructively, especially about the radiation shielding which is a unique problem of RI sample case. Also report about the result of the benchmark test measurement using $$^{241}$$Am $$gamma$$-ray standard source. Present study includes the result of "Research and Development for accuracy improvement of neutron nuclear data on minor actinides" entrusted to the Japan Atomic Energy Agency by the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT).

Journal Articles

Current activities and future plans for nuclear data measurements at J-PARC

Kimura, Atsushi; Harada, Hideo; Nakamura, Shoji; Iwamoto, Osamu; Toh, Yosuke; Koizumi, Mitsuo; Kitatani, Fumito; Furutaka, Kazuyoshi; Igashira, Masayuki*; Katabuchi, Tatsuya*; et al.

European Physical Journal A, 51(12), p.180_1 - 180_8, 2015/12

 Percentile:100(Physics, Nuclear)

Journal Articles

Accuracy improvement of neutron nuclear data on minor actinides

Harada, Hideo; Iwamoto, Osamu; Iwamoto, Nobuyuki; Kimura, Atsushi; Terada, Kazushi; Nakao, Taro; Nakamura, Shoji; Mizuyama, Kazuhito; Igashira, Masayuki*; Katabuchi, Tatsuya*; et al.

EPJ Web of Conferences (Internet), 93, p.06001_1 - 06001_5, 2015/05

 Times Cited Count:3 Percentile:10.3

Improvement of accuracy of neutron nuclear data for minor actinides (MAs) and long-lived fission products (LLFPs) is required for developing innovative nuclear system transmuting these nuclei. In order to meet the requirement, the project entitled as "Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC)" has been started as one of the "Innovative Nuclear Research and Development Program" at October 2013. The AIMAC project team is composed of researchers in four different fields: differential nuclear data measurement, integral nuclear data measurement, nuclear chemistry, and nuclear data evaluation. By integrating all of the forefront knowledge and techniques in these fields, the team aims at improving the accuracy of the data. The background, overall plan, and recent progress of the AIMAC project will be reviewed.

Journal Articles

Research and development for accuracy improvement of neutron nuclear data on minor actinides

Harada, Hideo

Kaku Deta Nyusu (Internet), (109), p.44 - 47, 2014/10

Improvement of accuracy of neutron nuclear data for minor actinides (MAs) and long-lived fission products (LLFPs) is required for developing innovative nuclear system transmuting these nuclei. In order to meet the requirement, the project entitled as "Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC)" has been started as one of the "Innovative Nuclear Research and Development Program". The AIMAC project team is composed of researchers in four different fields: differential nuclear data measurement, integral nuclear data measurement, nuclear chemistry, and nuclear data evaluation. By integrating all of the forefront knowledge and techniques in these fields, the research project team aims at improving the accuracy of the data. The background, goal and brief research plan of the AIMAC project are explained.

Journal Articles

Design optimization of ADS plant proposed by JAERI

Saito, Shigeru; Tsujimoto, Kazufumi; Kikuchi, Kenji; Kurata, Yuji; Sasa, Toshinobu; Umeno, Makoto*; Nishihara, Kenji; Mizumoto, Motoharu; Ouchi, Nobuo; Takei, Hayanori; et al.

Nuclear Instruments and Methods in Physics Research A, 562(2), p.646 - 649, 2006/06

 Times Cited Count:19 Percentile:16.39(Instruments & Instrumentation)

JAERI is conducting R&D on the Accelerator Driven System (ADS) to transmute minor actinides (MAs) contained in the high-level radioactive waste under the OMEGA (Options Making Extra Gains from Actinides and fission products) program. The present study discusses the design of the ADS plant and various R&D on the ADS. The reference design of ADS plant in JAERI is the 800 MWth, Pb-Bi eutectic (LBE) cooled, tank-type subcritical reactor loaded with (MA+Pu) nitride fuel. LBE is selected as a spallation target material. In our results of the optimization study on the neutronics of the ADS, we have adopted the maximum multiplication factor (k$$_{eff}$$) of 0.97. From the results of the thermal-hydraulic analysis around the LBE spallation target, partition wall and flow control nozzle are required to keep the structural integrity around the core and the beam window. Feasibility of beam window was also discussed for transient conditions of proton beam.

Journal Articles

Development of the ERIX process for reprocessing spent FBR-MOX fuel; A Study on minor actinides separation process

Hoshi, Harutaka*; Wei, Y.*; Kumagai, Mikio*; Asakura, Toshihide; Morita, Yasuji

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

For the development of nuclear fuel cycle, it is one of the most important tasks to improve reprocessing more economically and efficiently. Especially, to establish the Fast Breeder Reactor (FBR) cycle system for the future, it is strongly desirable to develop a new reprocessing which uses more compact equipments and produces less radioactive wastes compared to the present PUREX process. For this purpose, we have proposed a novel aqueous reprocessing system named ERIX Process to treat spent FBR-MOX fuels. This process consists of (1) Pd removal by selective adsorption using a specific anion exchanger; (2) electrolytic reduction for the valence adjustment of the major actinides including U, Pu, Np and some fission products (FP) such as Tc and Ru; (3) anion exchange separation for the recovery of U, Pu and Np using a new type of anion exchanger, AR-01; and (4) selective separation of long-lived minor actinides (MA = Am and Cm) by extraction chromatography. In this work, MA separation process was studied.

Journal Articles

Simulation of 4$$pi$$ Ge spectrometer by Geant4

Goto, Jun; Sugawara, Masahiko*; Oshima, Masumi; Toh, Yosuke; Kimura, Atsushi; Osa, Akihiko; Koizumi, Mitsuo; Mizumoto, Motoharu; Osaki, Toshiro*; Igashira, Masayuki*; et al.

AIP Conference Proceedings 769, p.788 - 791, 2005/05

no abstracts in English

Journal Articles

Research and development activities for accelerator driven system at JAERI

Tsujimoto, Kazufumi; Sasa, Toshinobu; Nishihara, Kenji; Oigawa, Hiroyuki; Takano, Hideki*

Proceedings of International Conference on Physics of Fuel Cycles and Advanced Nuclear Systems; Global Developments (PHYSOR 2004) (CD-ROM), 8 Pages, 2004/04

The Japan Atomic Energy Research Institute (JAERI) is developing an Accelerator Driven System (ADS) for transmutation of nuclear waste such as minor actinide (MA) and long-lived fission product (LLFP). To study and evaluate the feasibility of ADS by physical and engineering viewpoints, the Transmutation Experimental Facility (TEF) is proposed under a framework of J-PARC (Japan Proton Accelerator Research Complex) project. The TEF consists of two facilities named as Transmutation Physics Experimental Facility (TEF-P) and ADS Target Test Facility (TEF-T). The TEF-P consists of a zero-power critical assembly which is operated with a low power proton beam to research the reactor physics and the controllability of ADS. The TEF-T is a facility for material irradiation and partial mockup of beam window which can accept a maximum 600MeV-200kW proton beam into the Pb-Bi eutectic target. The purposes, experimental items and the specifications of the facilities are described.

Journal Articles

Neutronics design for lead-bismuth cooled accelerator-driven system for transmutation of minor actinide

Tsujimoto, Kazufumi; Sasa, Toshinobu; Nishihara, Kenji; Oigawa, Hiroyuki; Takano, Hideki

Journal of Nuclear Science and Technology, 41(1), p.21 - 36, 2004/01

 Times Cited Count:96 Percentile:0.96(Nuclear Science & Technology)

Neutronics design study was performed for lead-bismuth cooled accelerator-driven system (ADS) to transmute minor actinides. Early study for ADS indicated two problems: a large burnup reactivity swing and a significant peaking factor. To solve these problems, effect of design parameters on neutronics characteristics were searched. Parametric survey calculations were performed considering fuel cycle consisting of burnup and recycle. The results showed that burnup reactivity swing depends on the plutonium fraction in the initial fuel loading, and the lead-bismuth buffer region and the two-zone loading were effective for solving the problems. Moreover, an optimum value for the effective multiplication factor was also evaluated using reactivity coefficients. From the result, the maximum allowable value of the effective multiplication factor for a practical ADS can be set at 0.97. Consequently, a new core concept combining the buffer region and the two-zone loading was proposed base on the results of the parametric survey.

JAEA Reports

Comparison of fission and capture cross sections of minor actinides

Nakagawa, Tsuneo; Iwamoto, Osamu

JAERI-Data/Code 2002-025, 134 Pages, 2003/01

JAERI-Data-Code-2002-025.pdf:3.48MB

no abstracts in English

JAEA Reports

Conceptual study of transmutation experimental facility, 3; Study on transmutation physics experiment facility

Oigawa, Hiroyuki; Maekawa, Fujio; Meigo, Shinichiro; Kasugai, Yoshimi; Tsujimoto, Kazufumi; Nishihara, Kenji; Sasa, Toshinobu; Konno, Chikara; Kai, Tetsuya; Ikeda, Yujiro

JAERI-Tech 2002-037, 220 Pages, 2002/03

JAERI-Tech-2002-037.pdf:11.09MB

no abstracts in English

Journal Articles

Experiment for accelerator-driven transmutation

Oigawa, Hiroyuki

Nippon Butsuri Gakkai-Shi, 56(10), p.749 - 754, 2001/11

no abstracts in English

Journal Articles

Comparison of the burnup charcteristics and radiotoxicity hazards of rock-like oxide fuel with different types of additives

Shelley, A.*; Akie, Hiroshi; Takano, Hideki; Sekimoto, Hiroshi*

Journal of Nuclear Science and Technology, 38(2), p.134 - 142, 2001/02

no abstracts in English

Journal Articles

Radiotoxicity hazard of inert matrix fuels after burning minor actinides in light water reactors

Shelley, A.*; Akie, Hiroshi; Takano, Hideki; Sekimoto, Hiroshi*

Progress in Nuclear Energy, 38(3-4), p.439 - 442, 2001/02

 Times Cited Count:6 Percentile:51.33

no abstracts in English

Journal Articles

Transmutation of long-lived radioactive waste based on double-strata concept

Takano, Hideki; Nishihara, Kenji; Tsujimoto, Kazufumi; Sasa, Toshinobu; Oigawa, Hiroyuki; Takizuka, Takakazu

Progress in Nuclear Energy, 37(1-4), p.371 - 376, 2000/12

 Times Cited Count:15 Percentile:27.3

no abstracts in English

JAEA Reports

Conceptual study of transmutation experimental facility, 1; Outline of transmutation physics experiment facility

Oigawa, Hiroyuki; Ikeda, Yujiro; Sasa, Toshinobu; Meigo, Shinichiro; Takano, Hideki; Tsujimoto, Kazufumi; Nishihara, Kenji

JAERI-Tech 2000-062, 64 Pages, 2000/09

JAERI-Tech-2000-062.pdf:4.25MB

no abstracts in English

Journal Articles

Parametric studies on plutonium transmutation using uranium-free fuels in light water reactors

Afroza, S.*; Akie, Hiroshi; Takano, Hideki; Sekimoto, Hiroshi*

Nuclear Technology, 131(2), p.197 - 209, 2000/08

 Times Cited Count:2 Percentile:78.35(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Expansion of material balance analysis function on nuclear fuel cycle

Ohtaki, Akira; ; ; *; *;

JNC-TN9410 2000-006, 74 Pages, 2000/04

JNC-TN9410-2000-006.pdf:3.01MB

To evaluate materials balance in nuclear fuel cycle quickly and quantitatively the fuel cycle requirement code "FAMILY" was improved. And an accumulated TRU&LLFP quantity analysis code was developed. The contents are as follows: (1)A calculation ability of minor actinide production and expenditure was added to the "FAMILY" code. (2)An output program for the "FAMILY" calculation results was developed. (3)A simple version of "FAMILY" code was developed. (4)An analysis code for accumulated TRU&LLFP quantity in nuclear fuel cycle was developed.

JAEA Reports

Analysis of Cm contained in irradiated fuel of experimental fast reactor "JOYO"; Development of the analytical technique and measurement of Cm

Osaka, Masahiko; Koyama, Shinichi; Mitsugashira, Toshiaki; ;

JNC-TN9400 2000-058, 49 Pages, 2000/04

JNC-TN9400-2000-058.pdf:1.22MB

The analytical technique for Cm contained in a MOX FUEL was developed and analysis of Cm contained in irradiated fuel of experimental fast reactor "JOYO" was carried out, to contribute to evaluation of transmutation characteristics of MA nuclide in the fast reactor. The procedure of ion-exchange separation of Cm with nitric acid-methanol mixed media essential for the isotopic analysis in irradiated MOX fuel was adopted considering for being rapid and easy. The fundamental test to grasp separation characteristics of this procedure, such as Cm elution position and separation capacity between Cm and Am or Eu, was carried out. ln applying this procedure to the analysis of Cm contained in actual specimen, separation condition was evaluated and optimized, and the procedure consist of impurity removal and Am removal process was devised. This procedure resulted in high recovery rate of Cm and high removal rate of Am and impurity which becomes a problem in sample handling and mass-spectrometry such as Eu and Cs. The Cm separation test from irradiated MOX fuel was carried out using this technique, and Cm isotopic ratio analysis was enabled. The analytical technique for Cm contained in irradiated MOX fuel was established using the procedure of ion-exchange separation with nitric acid-methanol mixed media. The analysis of Cm contained in irradiated MOX fuel of experimental fast reactor "Joyo" was carried out. As a result, it was revealed from measured data that Cm content rate was 1.4$$sim$$ 4.0$$times$$lO$$^{-3}$$ atom%, small amount of $$^{247}$$Cm was generated and Cm isotopic ratio was constant above burn-up 60GWd/t.

69 (Records 1-20 displayed on this page)