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Journal Articles

Characterization of mechanical strain induced by lead-bismuth eutectic (LBE) freezing in stainless steel cup

Ohdaira, Naoya*; Saito, Shigeru

Heliyon (Internet), 6(2), p.e03429_1 - e03429_8, 2020/02

 Times Cited Count:4 Percentile:39.81(Multidisciplinary Sciences)

Lead-bismuth eutectic (LBE) is a candidate liquid metal coolant for a fast reactor, especially accelerator driven system (ADS). Freeze sealed valve is a candidate design to be possible to add passive safety to the reactor. On the other hand, since LBE is known that it causes expansion after its solidification, quantitative evaluation of the stress to the pipe produced by the LBE expansion should be considered. Many researchers produced related data for the expansion, however, evaluations of the strain by LBE expansion was barely reported. Therefore, the strain measurement using a stainless steel cup and the stress evaluation was performed together with visual observation using an optical microscopy. The results indicated keeping above room temperature (RT) was a significantly effective way to reduce the strain to the pipe.

Journal Articles

Present state of partitioning and transmutation of long-lived nuclides, 1; Significance of partitioning and transmutation and partitioning and transmutation systems

Minato, Kazuo; Tsujimoto, Kazufumi; Tanabe, Hiromi*; Fujimura, Koji*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 59(8), p.475 - 479, 2017/08

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:144 Percentile:99.24(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

Conceptual study of transmutation experimental facility, 4; Study on safety analysis of transmutation physics experiment facility

Tsujimoto, Kazufumi; Tazawa, Yujiro; Oigawa, Hiroyuki; Sasa, Toshinobu; Takano, Hideki

JAERI-Tech 2003-085, 158 Pages, 2003/11

JAERI-Tech-2003-085.pdf:7.79MB

A safety analysis was performed for the Transmutation Physics Experiment Facility which was to research and develop the reactor physics aspects of the nuclear transmutation technology using the accelerator driven subcritical system. Design policies were evaluated for design of each equipment and system which had important role from view point of safety. Classification of safety class for reactor building, system, and equipment was also reconsidered. Based on the results of safety design policy, acceptance criteria for safety evaluation were reestablished and preliminary analysis were performed. Public exposure by the accident for site appropriateness assessment was evaluated based on revised guidelines in safety evaluation contained in the 1990 Recommendations of ICRP. A recritical event was analyzed by utilizing the newest knowledge for core disruptive accident and calculation code as the beyond design basis accident. The analytical results showed that the isolation capability of the container buildings was ensured against the recritical accident.

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

Present status of research & development on accelerator-driven nuclear systems

Mukaiyama, Takehiko

Genshikaku Kenkyu, 44(6), p.23 - 32, 2000/04

no abstracts in English

Journal Articles

Conceptual design study and code development for accelerator-driven transmutation system

Tsujimoto, Kazufumi; Takizuka, Takakazu; Sasa, Toshinobu

Proc. of Int. Conf. on Future Nuclear Systems (Global'97), 1, p.435 - 439, 1997/00

no abstracts in English

Oral presentation

Review of research activities on partitioning and transmutation in Japan

Tsujimoto, Kazufumi

no journal, , 

The Government of Japan periodically formulates the Basic Energy Plan in accordance with an article in the Basic Act on Energy Policy that entered into force in 2002. The latest version, called the Strategic Energy Plan, was issued in April, 2014. The largest change from the previous versions must be the accident of the Fukushima Daiichi Nuclear Power Plant. In spite of the accident, the Plan defines the nuclear power as an important base-load power source as a low carbon and quasi-domestic energy source, contributing to stability of energy supply-demand structure, on major premise of ensuring of its safety. The Plan puts emphasis on the importance of activities to resolve the challenge of how to manage and dispose of spent fuel, as well as the Fukushima restoration, safety operation of nuclear plants, and public acceptance. As for the P&T technology, the Government will promote technology development on volume reduction and mitigation of degree of harmfulness of radioactive waste. Specifically, development of technologies for decreasing the radiation dose remaining in radioactive waste over a long period of time and enhancing the safety of processing and disposal of radioactive waste, including nuclear transmutation technology using fast reactors and accelerators, will be promoted by utilizing global networks for cooperation. Based on this new Strategic Energy Plan, research and development (R&D) on P&T are being accelerated in Japan. The Japan Atomic Energy Agency (JAEA) has been continuously implementing R&D on P&T technology to reduce the burden of the backend of the nuclear fuel cycle. The R&D on P&T in JAEA are basing on two kinds of concepts: one is the homogeneous recycling of minor actinide (MA) in fast reactors and the other is the dedicated MA transmutation, so-called double-strata strategy, using an accelerator-driven system (ADS). In this work, recent R&D activities based on these policies are briefly shown.

Oral presentation

Current status of R&D of accelerator-driven system for minor actinide transmutation in JAEA

Tsujimoto, Kazufumi

no journal, , 

To continue the utilization of the nuclear fission energy, the management of the high-level radioactive waste (HLW) is one of the most important issues to be solved. Partitioning and Transmutation (P&T) technology of HLW is expected to be effective to mitigate the burden of the HLW disposal by reducing the radiological toxicity and heat generation. The Japan Atomic Energy Agency (JAEA) has been conducting the research and development (R&D) on accelerator-driven subcritical system (ADS) as a dedicated system for the transmutation of long-lived radioactive nuclides. The ADS proposed by JAEA is a lead-bismuth eutectic (LBE) cooled fast subcritical reactor with thermal output of 800 MW. JAEA's reference design of ADS is a tank-type subcritical reactor, where lead-bismuth eutectic (LBE) is used as both the primary coolant and the spallation target. The central part of the core is the spallation target region. In the target region, LBE is flowing from the core bottom. The proton linac with the proton energy of 1.5 GeV is used for the accelerator to operate the ADS. A tank-type system is adopted to take advantage of a simple design and to eliminate the necessity of heavy primary piping. All primary components, including primary pumps, steam generators, and auxiliary heat exchangers, are accommodated within the reactor vessel. The primary cooling system includes two mechanical pumps and four steam generators. For the core fuel, (MA,Pu)-nitride is used. As inert matrix, zirconium-nitride (ZrN) is used with the fuel. Since the transmutation rate of MA is 250 kg/yr as described before, the relative transmutation efficiency of MA is about 10 %/yr. For ADS to play important roles in the nuclear fuel cycle, several critical issues have to be resolved. Items of R&D are divided into three technical areas peculiar to the ADS. For these technical areas, various R&D activities are progressing in JAEA.

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