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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

Overview of the PHITS code and application to nuclear data; Radiation damage calculation for materials

Iwamoto, Yosuke; Sato, Tatsuhiko; Niita, Koji*; Hashimoto, Shintaro; Ogawa, Tatsuhiko; Furuta, Takuya; Abe, Shinichiro; Kai, Takeshi; Matsuda, Norihiro; Iwase, Hiroshi*; et al.

JAEA-Conf 2016-004, p.63 - 69, 2016/09

A general purpose Monte Carlo Particle and Heavy Ion Transport code System, PHITS, is being developed through the collaboration of several institutes. PHITS can deal with the transport of nearly all particles, including neutrons, protons, heavy ions, photons, and electrons, over wide energy ranges using various nuclear reaction models and data libraries. PHITS users apply the code to various research and development fields such as nuclear technology, accelerator design, medical physics, and cosmic-ray research. This presentation briefly summarizes the physics models implemented in PHITS, and introduces some new models such as muon-induced nuclear reaction model and a $$gamma$$ de-excitation model EBITEM. We will also present the radiation damage cross sections for materials, PKA spectra and kerma factors calculated by PHITS under the IAEA-CRP activity titled "Primary radiation damage cross section."

Journal Articles

Reaction rate distribution measurement and analysis for 0.895 and 1.21GeV proton bombardment on thick tungsten target

Takada, Hiroshi; Meigo, Shinichiro; Sasa, Toshinobu; Fukahori, Tokio; Sakamoto, Yukio; Yoshizawa, Nobuaki*; Furihata, Shiori*; V.I.Belyakov-Bodin*; G.I.Krupny*

Proc. of 3rd Workshop on Simulating Accelerator Radiation Environments (SARE3), p.255 - 263, 1997/00

no abstracts in English

Journal Articles

Measurement of reaction rate distributions in a lead assembly bombarded with 500 MeV protons

Takada, Hiroshi; Meigo, Shinichiro; Sasa, Toshinobu; Tsujimoto, Kazufumi; Fukahori, Tokio; Yasuda, Hideshi

Proc. of 3rd Workshop on Simulating Accelerator Radiation Environments (SARE3), p.284 - 292, 1997/00

no abstracts in English

Journal Articles

Analysis of reaction rate distributions on a thick tungsten target bombarded with protons of 0.8 to 1.2GeV

Takada, Hiroshi; Meigo, Shinichiro; Sasa, Toshinobu; Fukahori, Tokio; V.I.Belyakov-Bodin*; G.I.Krupny*; Yu.E.Titarenko*

Proc. of 4th Int. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transm, 0, p.323 - 333, 1997/00

no abstracts in English

Journal Articles

Measurements of activation cross sections for the neutron dosimetry at an energy range from 17.5 to 30 MeV by using the $$^{7}$$Li(p,n) quasi-mono-energetic neutron source

Uno, Yoshitomo; Meigo, Shinichiro; Chiba, Satoshi; Fukahori, Tokio; Ikeda, Yujiro; Kasugai, Yoshimi; ; P.Siegler*

Proc. of 9th Int. Symp. on Reactor Dosimetry, 0, p.465 - 472, 1996/00

no abstracts in English

Oral presentation

Correlation between photoelectron emission and fragment recoil of methanol in intense laser fields

Fukahori, Shinichi*; Nakano, Motoyoshi; Yamanouchi, Kaoru*; Itakura, Ryuji

no journal, , 

Dissociative ionization of methanol in an intense laser field is investigated using photoelectron-photoion coincidence momentum imaging. Energy and angular correlations between a photoelectron and a fragment ion reveal the ionization and subsequent electronic excitation processes. It is revealed that the photoelectron angular distributions correlated with the CH$$_3$$$$^+$$ formation strongly depend on the energy of the counterpart photoelectron.

Oral presentation

Correlation between photoelectron emission and fragment recoil of methanol in an intense laser field

Fukahori, Shinichi*; Nakano, Motoyoshi; Yamanouchi, Kaoru*; Itakura, Ryuji

no journal, , 

Dissociative ionization of methanol is investigated. We confirm the presence of the two types of ionization and electronic excitation pathways based on the channel-specific photoelectron spectra and the energy correlation between the photoelectron and the fragment recoil. Furthermore, from the three dimensional momenta of the photoelectron and the CH$$_3^{+}$$ fragment ion detected in coincidence, energy-resolved molecular-frame photoelectron angular distributions are obtained.

Oral presentation

Momentum correlation between photoelectrons and fragment ions in dissociative ionization of methanol in intense laser fields

Fukahori, Shinichi*; Nakano, Motoyoshi; Yamanouchi, Kaoru*; Itakura, Ryuji

no journal, , 

We investigate the mechanism of the electronic excitation of singly charged methanol cation in dissociative ionization of methanol cation in intense laser fields based on photoelectron-photoion coincidence momentum imaging. From three independent experimental results such as (1) channel specific photoelectron spectra, (2) energy correlation of photoelectrons and fragment ions and (3) angular correlation of electron emission and fragment recoil, two types of ionization and electronic excitation pathways are revealed.

Oral presentation

Angular correlation between photoelectron emission and fragment recoil of methanol in an intense laser field

Fukahori, Shinichi*; Nakano, Motoyoshi*; Yamanouchi, Kaoru*; Itakura, Ryuji

no journal, , 

We investigate dissociative ionization of methanol in an intense laser field using photoelectron-photoion coincidence momentum imaging. We have measured channel-specific photoelectron angular distibutions as well as photoelectron energy spectra and energy correlations between photoelectrons and fragment ions. It is revealed that the photoelectron angular distributions reflect the character of the electronic states prepared at the photoelectron emission.

Oral presentation

R&D for introducing advanced fuels contributing to safety improvement of current LWRs, 1; Overview of project

Yamashita, Shinichiro; Ioka, Ikuo; Nemoto, Yoshiyuki; Shirasu, Noriko; Kurata, Masaki; Kaji, Yoshiyuki; Fukahori, Tokio; Watanabe, Seiichi*; Kirimura, Kazuki*; Kakiuchi, Kazuo*; et al.

no journal, , 

Since the accident at Fukushima Daiichi Nuclear Power Station, enhancing the accident tolerance of Light Water Reactors (LWRs) became a topic of serious discussion, and the research and development (R&D) for improving the safety LWRs has been activated in many countries. In Japan, the R&D project on accident tolerant fuel and other components (ATFs) of LWRs, which is sponsored and organized by the Ministry of Economy, Trade and Industry (METI), has been initiated in 2015 for establishing technical basis of ATFs. The Japan Atomic Energy Agency (JAEA) has coordinated and carried out this ATF R&D project in cooperation with power plant providers, fuel venders and universities for making the best use of the experiences, knowledges in commercial uses of zirconium-base alloys in LWRs.

Oral presentation

R&D for introducing advanced fuels contributing to safety improvement of current LWRs, 1; Overview of project

Yamashita, Shinichiro; Ioka, Ikuo; Nemoto, Yoshiyuki; Shirasu, Noriko; Kurata, Masaki; Kaji, Yoshiyuki; Fukahori, Tokio; Watanabe, Seiichi*; Murakami, Nozomu*; Sato, Hisaki*; et al.

no journal, , 

Since the accident at Fukushima Daiichi Nuclear Power Station, enhancing the accident tolerance of Light Water Reactors (LWRs) became a topic of serious discussion, and the research and development for improving the safety LWRs has been activated in many countries. This project is one of the projects that entrusted from the Ministry of Economy, Trade and Industry Agency for Natural Resources and Energy. Using a domestic human source, an analysis tool, know-how and experience, the basic technique to apply an accident tolerant fuel material to an existing LWRs is developed in the project. It is started from October, 2015 and is carrying out this project continuously.

Oral presentation

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

Sakamoto, Kan*; Ukai, Shigeharu*; Kimura, Akihiko*; Yamaji, Akifumi*; Kusagaya, Kazuyuki*; Kondo, Takao*; Yamashita, Shinichiro; Fukahori, Tokio

no journal, , 

Using the acquired material data by 2016, the feasibility of the reactor core, accident progress relaxation effect at an accident and a severe accident were confirmed by various analysis when Zircaloy replaced to FeCrAl-ODS steel. The results including the post irradiation examination in fiscal year 2017 will be introduced by this presentation.

Oral presentation

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

Sato, Hisaki*; Kakiuchi, Kazuo*; Ishibashi, Ryo*; Ikegawa, Tomohiko*; Kondo, Takao*; Yamashita, Shinichiro; Fukahori, Tokio

no journal, , 

SiC composite materials applied to a cladding tube and a channel box for BWR have been developed for introduction of the accident tolerant fuel to an existing LWRs. The outline of the outcome in fiscal year 2017 will be introduced by this presentation.

Oral presentation

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

Watanabe, Seiichi*; Sato, Daiki*; Furumoto, Kenichiro*; Murakami, Nozomu*; Yamashita, Shinichiro; Fukahori, Tokio

no journal, , 

SiC composite material is one of the candidate material as the accident tolerant fuel. The acquisition of the irradiation properties, the evaluation of fuel design and accident safety are main problems for the SiC composite material. For the solution, out- and in-pile testings of SiC composite, development of evaluation technique of fuel behavior, core characteristic and the safety at accident, analyses and evaluations by using the developed techniques have been carried out.

Oral presentation

R&D of advanced stainless steels for BWR fuel claddings, 3-4; Endurance for fuel failure under normal operation condition

Miura, Yusuke*; Sakamoto, Kan*; Yamashita, Shinichiro; Fukahori, Tokio

no journal, , 

Endurance for fuel failure under normal operation condition of FeCrAl ODS stainless steel was estimated as a part of research and development of the accident tolerant fuel. In this study, simple friction test and stress corrosion craking test under iodine environment were conducted and these results were compared with that of Zircaloy-2.

Oral presentation

The Feasibility study on SiC composite fuel cladding for the accident tolerant fuel to the existing PWR plants, 5; Evaluation of influence on core neutronics characteristics and fuel behavior

Murakami, Nozomu*; Kirimura, Kazuki*; Yamaji, Kazuya*; Sato, Daisuke*; Watanabe, Seiichi*; Sato, Daiki*; Furumoto, Kenichiro*; Yamashita, Shinichiro; Fukahori, Tokio

no journal, , 

The SiC/SiC composite has lower thermal conductivity than current Zry cladding, and it is necessary to raise a gap between the pellet and the cladding to prevent their contact from the viewpoint of pellet integrity. In the presentation, it will be reported that the effect of reduction of cladding diameter and hollow pellet on the temperature and the reactivity of the core.

Oral presentation

The Feasibility study on SiC composite fuel cladding for the accident tolerant fuel to the existing PWR plants, 6; Mechanical property test

Furumoto, Kenichiro*; Sato, Daiki*; Watanabe, Seiichi*; Yamashita, Shinichiro; Fukahori, Tokio

no journal, , 

The stress of SiC cladding to the existing PWR is important to evaluate the integrity of SiC cladding. It is necessary to comprehend mechanical properties of each of longitudinal and circumferential direction because there is anisotropy in mechanical properties of SiC cladding. The A-EDC test which was the circumferential direction mechanical test developed in recent years. The mechanical properties of SiC cladding in circumferential direction was measured using the A-EDC.

Oral presentation

The Feasibility study on SiC composite fuel cladding for the accident tolerant fuel to the existing PWR plants, 7; LOCA simulated test

Sato, Daiki*; Watanabe, Seiichi*; Komiyama, Daisuke*; Furumoto, Kenichiro*; Okamoto, Michiaki*; Yamato, Masaaki*; Yamashita, Shinichiro; Fukahori, Tokio

no journal, , 

It is expected that SiC cladding tube has high corrosion resistance and high strength under LOCA condition in existing PWR. There is little data for SiC cladding tube in the high temperature environment. So the apparatus which was capable of testing at LOCA simulated condition was manufactured for SiC cladding tube. The modified LOCA test was carried out for investigating the behavior of SiC cladding tube.

Oral presentation

R&D for introducing silicon carbide materials to safety improvement of BWR's core, 3; Plant transient analysis with SiC cladding fuel for RIA accident

Horie, Hideki*; Takeuchi, Yutaka*; Kakiuchi, Kazuo*; Sato, Hisaki*; Shirasu, Noriko; Saito, Hiroaki; Yamashita, Shinichiro; Fukahori, Tokio

no journal, , 

The problem in the accident tolerance fuel development was considered in comparison the fuel behavior of SiC/SiC composite cladding tube with current Zry cladding tube. In this study, Reactivity Initiated Accident (RIA) was evaluated using the plant excess security analysis code TRACTTM and the fuel performance code FEMAXI.

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