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Journal Articles

Overview of accident-tolerant fuel R&D program in Japan

Yamashita, Shinichiro; Ioka, Ikuo; Nemoto, Yoshiyuki; Kawanishi, Tomohiro; Kurata, Masaki; Kaji, Yoshiyuki; Fukahori, Tokio; Nozawa, Takashi*; Sato, Daiki*; Murakami, Nozomu*; et al.

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.206 - 216, 2019/09

After the nuclear accident at Fukushima Daiichi Power Plant, research and development (R&D) program for establishing technical basis of accident-tolerant fuel (ATF) started from 2015 in Japan. Since then, both experimental and analytical studies necessary for designing a new light water reactor (LWR) core with ATF candidate materials are being conducted within the Japanese ATF R&D Consortium for implementing ATF to the existing LWRs, accompanying with various technological developments required. Until now, we have accumulated experimental data of the candidate materials by out-of-pile tests, developed fuel evaluation codes to apply to the ATF candidate materials, and evaluated fuel behavior simulating operational and accidental conditions by the developed codes. In this paper, the R&D progresses of the ATF candidate materials considered in Japan are reviewed based on the information available such as proceedings of international conference and academic papers, providing an overview of ATF program in Japan.

Journal Articles

Establishment of technical basis to implement accident tolerant fuels and components to existing LWRs

Yamashita, Shinichiro; Nagase, Fumihisa; Kurata, Masaki; Kaji, Yoshiyuki

Proceedings of Annual Topical Meeting on LWR Fuels with Enhanced Safety and Performance (TopFuel 2016) (USB Flash Drive), p.21 - 30, 2016/09

Fuel rod, channel box, and control rod designed with new materials and concepts have been developed in Japan for increasing accident tolerance of LWRs. In order to efficiently and properly implement the accident tolerant fuels (ATFs) and the other components, it is necessary not only to accumulate fundamental and practical data but also to consider technology readiness, recognize knowledge gaps, and establish strategy for design and fabrication. The Japan Atomic Energy Agency (JAEA) has established the above "technical basis" and drafted a research plan towards implementation of the ATFs and components as a program sponsored and organized by the Ministry of Economy, Trade and Industry (METI). It is useful to take advantage of the experiences in commercial uses of zirconium-base alloys in LWRs and, therefore, JAEA has conducted this METI project in cooperation with power plant providers, fuel venders, research institutes and universities who have been involved in the development of the ATF materials. The present paper describes the main results of the project conducted to establish the technical basis of the ATFs and components.

Journal Articles

Experimental study for the production cross sections of positron emitters induced from $$^{12}$$C and $$^{16}$$O nuclei by low-energy proton beams

Akagi, Takashi*; Yagi, Masashi*; Yamashita, Tomohiro*; Murakami, Masao*; Yamakawa, Yoshiyuki*; Kitamura, Keiji*; Ogura, Koichi; Kondo, Kiminori; Kawanishi, Shunichi*

Radiation Measurements, 59, p.262 - 269, 2013/12

 Times Cited Count:6 Percentile:45.96(Nuclear Science & Technology)

In proton therapy, positron emitters are induced from $$^{12}$$C and$$^{16}$$O nuclei by protons on the beam path in the patient. Many studies for monitoring positron emitters with beam-induced PET technique have been performed by various groups to verify the proton beam range and the dose in the patient for quality assurance. The aim of this study was to develop a method for measuring the production cross sections of positron emitters using standard equipment for proton therapy. The time-activity curve was then obtained with a high-sensitivity PET scanner to extract the number of positron emitters produced in the target. The production cross sections for four reaction channels: $$^{16}$$O(p,pn)$$^{15}$$O, $$^{16}$$O(p,3p3n)$$^{11}$$C, $$^{16}$$O(p,2p2n)$$^{13}$$N, and $$^{12}$$C(p,pn)$$^{11}$$C were then measured. The cross sections for the $$^{16}$$O(p,pn)$$^{15}$$O reaction channel were consistent with data of previous experiments within the uncertainties, while those of $$^{12}$$C(p,pn)$$^{11}$$C were generally lower than data of previous experiments.

Journal Articles

Role of residual transition-metal atoms in oxygen reduction reaction in cobalt phthalocyanine-based carbon cathode catalysts for polymer electrolyte fuel cell

Kobayashi, Masaki*; Niwa, Hideharu*; Harada, Yoshihisa*; Horiba, Koji*; Oshima, Masaharu*; Ofuchi, Hironori*; Terakura, Kiyoyuki*; Ikeda, Takashi; Koshigoe, Yuka*; Ozaki, Junichi*; et al.

Journal of Power Sources, 196(20), p.8346 - 8351, 2011/10

 Times Cited Count:27 Percentile:30.32(Chemistry, Physical)

The electronic structure of Co atoms in CoPc-based carbon catalysts, which were prepared by pyrolyzing a mixture of CoPc and phenol resin polymer up to 1000$$^circ$$C, has been investigated using XAFS analysis and HXPES. The Co K XAFS spectra show that most of the Co atoms are in the metallic state and small quantities of oxidized Co components are present in the samples even after acid washing to remove Co atoms. Based on the difference in probing depth between XAFS and HXPES, it was found that after acid washing, the surface region with the aggregated Co clusters is primarily composed of metallic Co. Since the electrochemical properties remain almost unchanged even after the acid washing process, the residual metallic and oxidized Co atoms themselves will hardly contribute to the ORR activity of the CoPc-based carbon cathode catalysts, implying that the active sites of the CoPc-based catalysts primarily consist of light elements such as C and N.

Journal Articles

Conduction-band electronic states of YbInCu$$_4$$ studied by photoemission and soft X-ray absorption spectroscopies

Utsumi, Yuki*; Sato, Hitoshi*; Kurihara, Hidenao*; Maso, Hiroyuki*; Hiraoka, Koichi*; Kojima, Kenichi*; Tobimatsu, Komei*; Okochi, Takuo*; Fujimori, Shinichi; Takeda, Yukiharu; et al.

Physical Review B, 84(11), p.115143_1 - 115143_7, 2011/09

 Times Cited Count:6 Percentile:66.41(Materials Science, Multidisciplinary)

We have studied conduction-band (CB) electronic states of a typical valence-transition compound YbInCu$$_4$$ by means of temperature-dependent hard X-ray photoemission spectroscopy (HX-PES), soft X-ray absorption spectroscopy (XAS), and soft X-ray photoemission spectroscopy (SX-PES) of the valence band. We have described the valence transition in YbInCu$$_4$$ in terms of the charge transfer from the CB to Yb 4$$f$$ states.

Journal Articles

X-ray photoemission spectroscopy analysis of N-containing carbon-based cathode catalysts for polymer electrolyte fuel cells

Niwa, Hideharu*; Kobayashi, Masaki*; Horiba, Koji*; Harada, Yoshihisa*; Oshima, Masaharu*; Terakura, Kiyoyuki*; Ikeda, Takashi; Koshigoe, Yuka*; Ozaki, Junichi*; Miyata, Seizo*; et al.

Journal of Power Sources, 196(3), p.1006 - 1011, 2011/02

 Times Cited Count:76 Percentile:7.29(Chemistry, Physical)

We report on the electronic structure of three different types of N-containing carbon-based cathode catalysts for polymer electrolyte fuel cells observed by hard X-ray photoemission spectroscopy. C 1s spectra show the importance of $$sp^{2}$$ carbon network formation for the oxygen reduction reaction (ORR) activity. Samples having high oxygen reduction reaction activity in terms of oxygen reduction potential contain high concentration of graphite-like nitrogen. Based on a quantitative analysis of our results, the oxygen reduction reaction activity of the carbon-based cathode catalysts will be improved by increasing concentration of graphite-like nitrogen in a developed $$sp^{2}$$ carbon network.

JAEA Reports

JAERI-JNC joint research report; A Study on degradation of structural materials used under the irradiation environment in nuclear reactors

Ueno, Fumiyoshi*; Nagae, Yuji; Nemoto, Yoshiyuki*; Miwa, Yukio*; Takaya, Shigeru; Hoshiya, Taiji; Tsukada, Takashi*; Aoto, Kazumi; Ishii, Toshimitsu*; Omi, Masao*; et al.

JNC-TY9400 2005-013, 150 Pages, 2005/09

JNC-TY9400-2005-013.pdf:37.33MB

None

JAEA Reports

JAERI-JNC joint research report; A Study on degradation of structural materials used under the irradiation environment in nuclear reactors

Ueno, Fumiyoshi; Nagae, Yuji*; Nemoto, Yoshiyuki; Miwa, Yukio; Takaya, Shigeru*; Hoshiya, Taiji*; Tsukada, Takashi; Aoto, Kazumi*; Ishii, Toshimitsu; Omi, Masao; et al.

JAERI-Research 2005-023, 132 Pages, 2005/09

JAERI-Research-2005-023.pdf:33.03MB

JAERI and JNC have started a JAERI-JNC joint research program in fiscal year 2003, which has been aimed for efficient progress and synergistic effect on the research activities in both Institutes. This study has been chosen one of the joint research themes because it has been our common objective in the field of structural materials of FBR and LWR components. The purpose of the study is to clarify damage mechanism of structural materials used under irradiation, and then to develop the methods for damage evaluation and detection in earlier stage of progressing process of damage. In fiscal year 2004 and 2005, micro-corrosion measurement, electrochemical corrosion test and leakage magnetic flux density measurement apparatuses were developed and equipped in two hot facilities and irradiated and unirradiated crept specimens, irradiated high purity model austenitic stainless alloys were also prepared and applied to this study. These apparatuses and specimens were used for damage evaluation, and these feasibilities for nuclear power plant materials were studied.

Journal Articles

First test results for the ITER central solenoid model coil

Kato, Takashi; Tsuji, Hiroshi; Ando, Toshinari; Takahashi, Yoshikazu; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Kawano, Katsumi; Oshikiri, Masayuki*; et al.

Fusion Engineering and Design, 56-57, p.59 - 70, 2001/10

 Times Cited Count:17 Percentile:24.03

no abstracts in English

Journal Articles

Progress of the ITER central solenoid model coil programme

Tsuji, Hiroshi; Okuno, Kiyoshi*; Thome, R.*; Salpietro, E.*; Egorov, S. A.*; Martovetsky, N.*; Ricci, M.*; Zanino, R.*; Zahn, G.*; Martinez, A.*; et al.

Nuclear Fusion, 41(5), p.645 - 651, 2001/05

 Times Cited Count:53 Percentile:15.63(Physics, Fluids & Plasmas)

no abstracts in English

Oral presentation

Development of an ECT sensor for SG tubes at high temperatures

Shiina, Akira; Yamashita, Takuya; Watanabe, Toshio; Imai, Yoshiyuki*; Ono, Koichi*

no journal, , 

no abstracts in English

Oral presentation

Activity of the Nuclear Human Resources Development Center in Japan Atomic Energy Agency

Yamashita, Kiyonobu; Murakami, Hiroyuki; Nakagawa, Norio; Arai, Nobuyoshi; Matsuura, Kenichi; Ozeki, Yoshiyuki

no journal, , 

The Nuclear Human Resource Development Center of the Japan Atomic Energy Agency (NuHRDeC/JAEA) has continuously and comprehensively conducted a variety of education and training courses in the nuclear field over a half century since its establishment (1958). The main recent activities are (1) Education and training for domestic nuclear engineers, (2) Education and training for foreign nuclear engineers, (3) Cooperation with domestic universities for nuclear education, (4) Cooperation with international organization for nuclear human resource development, and (5) Central role as secretariat for Japan Nuclear Human Resource Development Network (JN-HRD Net). These recent activity is reported in the meeting.

Oral presentation

Effect of electrochemical pre-treatment and interface structure between Pt and CeO$$_{x}$$ for improvement of oxygen reduction reaction activity on Pt-CeO$$_{x}$$ model electro catalysis

Fugane, Keisuke*; Mori, Toshiyuki*; Wu, Y. Y.*; Yamamoto, Shunya; Maekawa, Yasunari; Yoshikawa, Hideki*; Yamashita, Yoshiyuki*; Ueda, Shigenori*; Vladimir, M.*; Suzuki, Akira*; et al.

no journal, , 

no abstracts in English

Oral presentation

Fundamental studies to improve analysis of accident progression at Fukushima Daiichi NPP

Nagase, Fumihisa; Yoshida, Hiroyuki; Nemoto, Yoshiyuki; Amaya, Masaki; Yamashita, Shinichiro

no journal, , 

In order to conduct decommissioning of the Fukushima-Daiichi NPP properly and reliably, increase of accuracy is required in estimation of the accident progress and status inside the reactors. It is also required to improve analytical methods to estimate severe accident progression in the existing light water reactors. Therefore, JAEA conducts fundamental studies in terms of thermal hydraulic behaviour in reactor, fuel damage and degradation process, behaviour of structural materials and pressure vessel, release and migration of fission products, and so on under severe accident conditions. The present paper reports overview of the fundamental studies and recent results.

Oral presentation

Measurement of the free surface geometry on a curved open channel using color coding method

Ito, Takahiro*; Yamashita, Masatoshi*; Nishikawa, Masato*; Tsuji, Yoshiyuki*; Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Nakaniwa, Koichi

no journal, , 

no abstracts in English

Oral presentation

Fundamental studies related to accident progression analysis at Fukushima Daiichi NPP

Nagase, Fumihisa; Yoshida, Hiroyuki; Nemoto, Yoshiyuki; Amaya, Masaki; Yamashita, Shinichiro

no journal, , 

In order to conduct decommissioning of the Fukushima-Daiichi NPP properly and reliably, increase of accuracy is required in estimation of the accident progress and status inside the reactors. It is also required to improve analytical methods to estimate severe accident progression in the existing light water reactors. Therefore, JAEA conducts fundamental studies in terms of thermal hydraulic behaviour in reactor, fuel damage and degradation process, behaviour of structural materials and pressure vessel, release and migration of fission products, and so on under severe accident conditions. The present paper reports overview of the fundamental studies and recent results.

Oral presentation

Establishment of technical basis to implement accident tolerant fuels and components to existing LWRs; R&D program for design and fabrication towards implementation of ATFs and components to the existing LWRs

Yamashita, Shinichiro; Nagase, Fumihisa; Kurata, Masaki; Kaji, Yoshiyuki

no journal, , 

In TEPCO's Fukushima Daiichi Nuclear Power Station (1F), the cooling capability was lost due to tsunami caused by the Great East Japan Earthquake. It is considered that the Zirconium (Zr) alloy fuel cladding was oxidized in the heated core and the subsequent temperature escalation due to the oxidation caused core melting. As lessons learned from the 1F accident, development of advanced fuel and core components with enhanced accident tolerance becomes the greater concern. We have started R&D to establish the technical basis to implement the advanced fuel components to existing LWRs. The R&D is conducted in cooperation with power plant providers, fuel venders, research institutes and universities who have been involved in the development of the advanced fuel components. In this presentation, we will introduce the R&D program which are carried out under the Project on Development of Technical Basis for Safety Improvement at Nuclear Power Plants by Ministry of Economy, Trade and Industry (METI) of Japan.

Oral presentation

R&D for introducing advanced fuels contributing to safety improvement of current LWRs, 2; FeCrAl-ODS steels for BWR fuel claddings

Sakamoto, Kan*; Hirai, Mutsumi*; Ukai, Shigeharu*; Kimura, Akihiko*; Yamaji, Akifumi*; Kusagaya, Kazuyuki*; Kondo, Takao*; Ioka, Ikuo; Yamashita, Shinichiro; Kaji, Yoshiyuki

no journal, , 

no abstracts in English

Oral presentation

R&D for introducing advanced fuels contributing to safety improvement of current LWRs, 3; SiC composite material for BWR

Kakiuchi, Kazuo*; Sato, Hisaki*; Ishibashi, Ryo*; Kondo, Takao*; Ioka, Ikuo; Yamashita, Shinichiro; Kaji, Yoshiyuki

no journal, , 

no abstracts in English

Oral presentation

R&D for introducing advanced fuels contributing to safety improvement of current LWRs, 4; SiC composite material for PWR

Teshima, Hideyuki*; Watanabe, Seiichi*; Furumoto, Kenichiro*; Kirimura, Kazuki*; Yamakoshi, Yoshinori*; Ioka, Ikuo; Yamashita, Shinichiro; Kaji, Yoshiyuki

no journal, , 

no abstracts in English

28 (Records 1-20 displayed on this page)