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Journal Articles

Application of FE-SEM to the measurement of U, Pu, Am in the irradiated MA-MOX fuel

Sasaki, Shinji; Tanno, Takashi; Maeda, Koji

Proceedings of 54th Annual Meeting of Hot Laboratories and Remote Handling (HOTLAB 2017) (Internet), 6 Pages, 2017/00

During irradiation in a fast reactor, the microstructure change of the mixed oxide fuels and the changes of element distributions occur because of a radial temperature gradient. Therefore, it is important to study the irradiation behavior of MA-MOX for advancement of fast reactor fuels. In order to make detailed observations of microstructure and elemental analyses of MA-MOX, irradiated MA-MOX specimens were carried out PIE by using a FE-SEM equipped with WDX. Because fuel samples have high radio activities and emit alpha-particles, the instrument was modified. the instrument was installed in a lead shield box and the control unit was separately located outside the box. The microstructure changes were observed in irradiated MA-MOX specimen. The characteristic X-rays peaks were detected successfully. By measuring the intensities of characteristic X-rays, it was tried quantitative analysis of U, Pu, Am along radial direction of irradiated specimen.

JAEA Reports

Fabrication and test results of testing equipment for remote-handling of MA fuel, 3; Testing equipment for fuel loading

Tazawa, Yujiro; Nishihara, Kenji; Sugawara, Takanori; Tsujimoto, Kazufumi; Sasa, Toshinobu; Eguchi, Yuta; Kikuchi, Masashi*; Inoue, Akira*

JAEA-Technology 2016-029, 52 Pages, 2016/12

JAEA-Technology-2016-029.pdf:5.34MB

Transmutation Physics Experimental Facility (TEF-P) planned in the J-PARC project uses minor actinide (MA) fuels in the experiments. These MA fuels are highly-radioactive, so the fuel handling equipment in TEF-P is necessary to be designed as remote-handling system. This report summarizes fabrication and test results of the testing equipment for fuel loading that is one of components of the testing equipment for remote-handling of MA fuels. The testing equipment which had a remote-handling system for fuel loading was fabricated. And the test in combination with the mock-up core was performed. Through the test, it was confirmed to load/take the dummy fuel pin to/from the mock-up core without failure. It was shown that the concept design of the fuel loading equipment of TEF-P was reasonable.

JAEA Reports

Fabrication and test results of testing equipment for remote-handling of MA fuel, 1; Testing equipment for fuel cooling

Nishihara, Kenji; Tazawa, Yujiro; Inoue, Akira; Sugawara, Takanori; Tsujimoto, Kazufumi; Sasa, Toshinobu; Obayashi, Hironari; Yamaguchi, Kazushi; Kikuchi, Masashi*

JAEA-Technology 2015-051, 47 Pages, 2016/03

JAEA-Technology-2015-051.pdf:3.6MB

This report summarizes fabrication and test results of a testing equipment for fuel cooling that is a component of the testing equipment for remote-handling of highly-radioactive MA fuels in the transmutation physics experimental facility (TEF-P) planned in the J-PARC. Evaluation formula of pressure drop and temperature increase used in the design of TEF-P was validated by the test, and, feasibility of cooling concept was confirmed.

Journal Articles

Development of nitride fuel cycle technology for transmutation of minor actinides

Hayashi, Hirokazu; Nishi, Tsuyoshi*; Sato, Takumi; Kurata, Masaki

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1811 - 1817, 2015/09

Transmutation of long-lived radioactive nuclides including minor actinides (MA: Np, Am, Cm) has been studied in Japan Atomic Energy Agency (JAEA). Accelerator-driven system (ADS) is regarded as one of the powerful tools for transmutation of MA under the double strata fuel cycle concept. Uranium-free nitride fuel was chosen as the first candidate fuel for MA transmutation using ADS. To improve the transmutation ratio of MA, reprocessing of spent fuel and reusing MA recovered from the spent fuels is necessary. Our target is to transmute 99% of MA arisen from commercial power reactor fuel cycle, with which the period until the radiotoxicity drops below that of natural uranium can be shorten from about 5000 years to about 300 years. A pyrochemical process has been proposed as the first candidate for reprocessing of the spent nitride fuel. This paper overviews the current status of the nitride fuel cycle technology. Our recent study on fuel fabrication, fuel property measurements, reprocessing of spent fuel, development of the property database of MA nitride fuel, and fuel behavior simulation code are introduced. Our research and development (R&D) plan based on the roadmap of the development is also introduced.

Journal Articles

Properties of minor actinide compounds relevant to nuclear fuel technology

Minato, Kazuo; Takano, Masahide; Nishi, Tsuyoshi; Ito, Akinori; Akabori, Mitsuo

Recent Advances in Actinide Science, p.317 - 322, 2006/06

To reduce the radiotoxicity of the high-level waste and to use the repository efficiently, recycling of minor actinides (MA: Np, Am, Cm) as well as plutonium is an option for the future nuclear fuel cycle. For MA-bearing fuel development, new facilities with inert atmosphere were installed and the thermal properties of minor actinide compounds, especially nitrides and oxides, were measured. Minor actinide nitrides were prepared by carbothermic reduction of the oxides. Lattice parameter and its thermal expansion were measured by high-temperature X-ray diffraction, and thermal diffusivity by laser flash method.

Journal Articles

Present status and future perspective of research and development on partitioning and transmutation technology at JAERI

Oigawa, Hiroyuki; Minato, Kazuo; Kimura, Takaumi; Morita, Yasuji; Arai, Yasuo; Nakayama, Shinichi; Nishihara, Kenji

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

JAERI is engaging in the R&D on the Double-strata Fuel Cycle concept in accordance with the results of the check and review on the Partitioning and Transmutation (PT) technology made by the Atomic Energy Commission of Japan in 2000. As for the partitioning process, after the establishment of the "4-group Partitioning Process Concept", an innovative concept called ARTIST is also being studied. As for the fuel technology, minor actinide nitrides such as NpN and AmN were synthesized and their material properties have been measured. To reprocess the irradiated fuel, the pyrochemical process has been studied. The R&D of the accelerator-driven transmutation system are in progress for an accelerator, lead-bismuth, and a subcritical reactor. In addition, JAERI has started the high-intensity proton accelerator project (J-PARC), which includes the Transmutation Experimental Facility (TEF) as the Phase-II. The impact of PT technology on the backend of the nuclear energy utilization is also being discussed.

Journal Articles

Parametric survey on possible impact of partitioning and transmutation of high-level radioactive waste

Oigawa, Hiroyuki; Yokoo, Takeshi*; Nishihara, Kenji; Morita, Yasuji; Ikeda, Takao*; Takaki, Naoyuki*

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

The benefit of implementing Partitioning and Transmutation (P&T) of high-level wastes was parametrically surveyed. The possible reduction of the geological repository area was estimated. By recycling minor actinides (MA), the repository area required for unit spent fuel was reduced significantly in the case of MOX-LWR. This effect was caused by removal of $$^{241}$$Am which is a long-term heat source. By partitioning the fission products, in addition to MA recycling, further 70-80% reduction from the MA-recovery case can be expected for both UO$$_2$$ and MOX. This significant reduction was independent of the cooling time before the partitioning process.

Journal Articles

Research and development on accelerator-driven transmutation system at JAERI

Sasa, Toshinobu; Oigawa, Hiroyuki; Tsujimoto, Kazufumi; Nishihara, Kenji; Kikuchi, Kenji; Kurata, Yuji; Saito, Shigeru; Futakawa, Masatoshi; Umeno, Makoto*; Ouchi, Nobuo; et al.

Nuclear Engineering and Design, 230(1-3), p.209 - 222, 2004/05

 Times Cited Count:29 Percentile:12(Nuclear Science & Technology)

JAERI carries out research and development on accelerator-driven system (ADS) to transmute minor actinides and long-lived fission products. The system is composed of high intensity proton accelerator, lead-bismuth spallation target and lead-bismuth cooled subcritical core with nitride fuel. About 2,500 kg of minor actinide is loaded into the subcritical core. Annual transmutation amount using this system is 250 kg with 800MW of thermal output. A superconducting linear accelerator with the beam power of 30MW is connected to drive the subcritical core. Many research and development activities are under way and planned in the fields of subcritical core design, spallation target technology, lead-bismuth handling technology, accelerator development, and minor actinide fuel development. Especially, to study and evaluate the feasibility of the ADS from physics and engineering aspects, the Transmutation Experimental Facility (TEF) is proposed under a framework of the High-Intensity Proton Accelerator Project.

Journal Articles

Fabrication of nitride fuels for transmutation of minor actinides

Minato, Kazuo; Akabori, Mitsuo; Takano, Masahide; Arai, Yasuo; Nakajima, Kunihisa; Ito, Akinori; Ogawa, Toru

Journal of Nuclear Materials, 320(1-2), p.18 - 24, 2003/09

 Times Cited Count:48 Percentile:5.15

In the Japan Atomic Energy Research Institute, the concept of the transmutation of minor actinides (MA: Np, Am and Cm) with accelerator-driven systems is being studied. The MA nitride fuel has been chosen as a candidate because of the possible mutual solubility among the actinide mononitrides and excellent thermal properties besides supporting hard neutron spectrum. MA nitrides of AmN, (Am,Y)N, (Am,Zr)N and (Cm0.4Pu0.6)N were prepared from the oxides by the carbothermic reduction method. The prepared MA nitrides were examined by X-ray diffraction and the contents of impurities of oxygen and carbon were measured. The fabrication conditions for MA nitrides were improved so as to reduce the impurity contents. For an irradiation test of U-free nitride fuels, pellets of (Pu,Zr)N and PuN+TiN were prepared and a He-bonded fuel pin was fabricated. The irradiation test started in May 2002 and will go on for two years in the Japan Materials Testing Reactor.

Journal Articles

Research and development on nuclear transmutation, B; Transmutation fuel and reprocessing

Minato, Kazuo; Arai, Yasuo

Genshikaku Kenkyu, 47(6), p.31 - 38, 2003/06

no abstracts in English

Journal Articles

Research and development on accelerator-driven transmutation system at JAERI

Sasa, Toshinobu; Oigawa, Hiroyuki; Tsujimoto, Kazufumi; Nishihara, Kenji; Kikuchi, Kenji; Kurata, Yuji; Saito, Shigeru; Futakawa, Masatoshi; Umeno, Makoto*; Ouchi, Nobuo; et al.

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 9 Pages, 2003/04

JAERI carries out research and development on accelerator-driven system (ADS) to transmute minor actinides and long-lived fission products in high-level radioactive waste. The system is composed of high intensity proton accelerator, lead-bismuth spallation target and lead-bismuth cooled subcritical core with nitride fuel. About 2500 kg of minor actinide is loaded into the subcritical core. Annual transmutation amount using this system is 250 kg with 800MW of thermal output. A superconducting linear accelerator with the beam power of 20 - 30MW is connected to drive the subcritical core. The nitride fuel without uranium, such as (Np, Am, Pu)N, is selected. The fuel irradiated in the ADS is reprocessed by pyrochemical process followed by the re-fabrication of the fuel. Many research and development activities are under way. Especially, to study and evaluate the feasibility of the ADS from physics and engineering aspects, the Transmutation Experimental Facility (TEF) is proposed under a framework of the High-Intensity Proton Accelerator Project.

Journal Articles

Research and development on accelerator-driven system for transmutation of long-lived nuclear waste at JAERI

Oigawa, Hiroyuki; Sasa, Toshinobu; Takano, Hideki; Tsujimoto, Kazufumi; Nishihara, Kenji; Kikuchi, Kenji; Kurata, Yuji; Saito, Shigeru; Futakawa, Masatoshi; Umeno, Makoto*; et al.

Proceedings of 13th Pacific Basin Nuclear Conference (PBNC 2002) (CD-ROM), 8 Pages, 2002/10

To reduce the burden on the final disposal of the nuclear waste, the Acclelerator-Driven System (ADS) which can transmute minor actinides efficiently has been studied in JAERI. The proposed ADS design is an 800MWth subcritical core with lead-bismuth coolant and minor-actinide nitride fuel driven by a neutron source of a superconductivity linear accelerator with 30MW and a lead-bismuth spallation target. To realize the ADS, many research and development are under way in the fields of the accelerator, the spallation target and the nitride fuel. Moreover, a new experimental facility, the Transmutation Experimental Facility, is proposed under a framework of the High-Intensity Proton Accelerator Project to study the feasibility of the ADS from physics and engineering aspects.

Journal Articles

The Accelerator driven system strategy in Japan

Kurata, Yuji; Takizuka, Takakazu; Osugi, Toshitaka; Takano, Hideki

Journal of Nuclear Materials, 301(1), p.1 - 7, 2002/02

 Times Cited Count:10 Percentile:41.76

no abstracts in English

Journal Articles

Estimation of spent fuel compositions from light water reactors

Ando, Yoshihira*; Nishihara, Kenji; Takano, Hideki

Journal of Nuclear Science and Technology, 37(10), p.924 - 933, 2000/10

no abstracts in English

Journal Articles

The Current status of R&D for accelerator-driven system at JAERI

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

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 8 Pages, 2000/09

Japan Atomic Energy Research Institute (JAERI) performs research and development for accelerator-driven transmutation systems to improve the environmental impact and increase a capacity of waste disposal plant. The system consists of a superconducting proton LINAC, Pb-Bi eutectic spallation target and Pb-Bi cooled subcritical core. Thermal output of the system is 800MW by injection of the proton beam with the power of 20 to 30MW and then, about 250kg of minor actinides can be transmuted annually. To study and evaluate the feasibility of ADS by a physical and an engineering viewpoint, the Transmutation Experimental Facility is proposed under a framework of J-PARC project. In the presentation, the R&D activities by the contract between the Ministry of Education, Culture, Sports, Science and Technology will be presented.

Journal Articles

HTGR type minor actinide transmutation reactor

Fujimoto, Nozomu; Yamashita, Kiyonobu; *

Nippon Genshiryoku Gakkai-Shi, 38(4), p.304 - 306, 1996/00

no abstracts in English

Journal Articles

Delayed neutron emission measurements from fast fission of U-235 and NP-237

W.S.Charlton*; T.A.Parish*; S.Raman*; Shinohara, Nobuo; Ando, Masaki

PHYSOR 96: Int. Conf. on the Physics of Reactors, 3, p.F11 - F20, 1996/00

no abstracts in English

Journal Articles

Dense fuel cycles for actinide burning and thermodynamic database

Ogawa, Toru; ; Kobayashi, Fumiaki; Ito, Akinori; Mukaiyama, Takehiko; Handa, Nuneo; R.G.Haire*

Global 1995,Int. Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems, 1, p.207 - 214, 1995/00

no abstracts in English

Oral presentation

Fuel technology development for partitioning and transmutation of minor actinide (MA), 1; Current status and issues in MA-bearing oxide fuel development

Tanaka, Kosuke

no journal, , 

Current status and issues in minor actinide (MA)-Bearing oxide fuel development are summarised as a part of partitioning and transmutation of MA.

Oral presentation

Fuel cycle for MA transmutation based on nitride fuel and pyrochemical reprocessing

Takano, Masahide

no journal, , 

Concept and R&D status of the fuel cycle for MA transmutation based on nitride fuel and pyrochemical reprocessing are introduced in this lecture. Outline of our achievements in fabrication technologies for MA-bearing nitride fuel, thermal properties and establishment of the database, development of the nitride fuel performance code, issues of helium accumulation, and enrichment of nitrogen 15 is shown with the future plan for irradiation test and post-irradiation examination.

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