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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

Electron-tracking Compton camera imaging of technetium-95m

Hatsukawa, Yuichi*; Hayakawa, Takehito*; Tsukada, Kazuaki; Hashimoto, Kazuyuki*; Sato, Tetsuya; Asai, Masato; Toyoshima, Atsushi; Tanimori, Toru*; Sonoda, Shinya*; Kabuki, Shigeto*; et al.

PLOS ONE (Internet), 13(12), p.e0208909_1 - e0208909_12, 2018/12

AA2018-0639.pdf:2.39MB

 Times Cited Count:2 Percentile:30.45(Multidisciplinary Sciences)

Imaging of $$^{95m}$$Tc radioisotope was conducted using an electron tracking-Compton camera (ETCC). $$^{95m}$$Tc emits 204, 582, and 835 keV $$gamma$$ rays, and was produced in the $$^{95}$$Mo(p,n)$$^{95m}$$Tc reaction with a $$^{95}$$Mo-enriched target. The recycling of the $$^{95}$$Mo-enriched molybdenum trioxide was investigated, and the recycled yield of $$^{95}$$Mo was achieved to be 70% - 90%. The images were obtained with each of the three $$gamma$$ rays. Results showed that the spatial resolution increases with increasing $$gamma$$-ray energy, and suggested that the ETCC with high-energy $$gamma$$-ray emitters such as $$^{95m}$$Tc is useful for the medical imaging of deep tissue and organs in the human body.

Journal Articles

Technical basis of accident tolerant fuel updated under a Japanese R&D project

Yamashita, Shinichiro; Nagase, Fumihisa; Kurata, Masaki; Nozawa, Takashi; Watanabe, Seiichi*; Kirimura, Kazuki*; Kakiuchi, Kazuo*; Kondo, Takao*; Sakamoto, Kan*; Kusagaya, Kazuyuki*; et al.

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09

In Japan, the research and development (R&D) project on accident tolerant fuel and other components (ATFs) of light water reactors (LWRs) 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 (Zircaloy) in LWRs. ATF candidate materials under consideration in the project are FeCrAl steel strengthened by dispersion of fine oxide particles(FeCrAl-ODS) and silicon carbide (SiC) composite, and are expecting to endure severe accident conditions in the reactor core for a longer period of time than the Zircaloy while maintaining or improving fuel performance during normal operations. In this paper, the progresses of the R&D project are reported.

Journal Articles

Welding technology R&D of Japanese accident tolerant fuel claddings of FeCrAl-ODS steel for BWRS

Kimura, Akihiko*; Yuzawa, Sho*; Sakamoto, Kan*; Hirai, Mutsumi*; Kusagaya, Kazuyuki*; Yamashita, Shinichiro

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09

The effect of Al addition on the PRW weldability of ODS steel is shown with the discussion focusing on the microstructure changes by the welding. The ordinary welding methods including electron beam (EB) welding and tungsten inert gas (TIG) welding were also applied to the SUS430 endcap welding to cladding tube made of FeCrAl-ODS steel. The endcap welded ODS steel tube samples were tensile tested at RT. The EB welded FeCrAl-ODS/SUS430 samples broke in the ODS steel tube, indicating that the weld bond is stronger than the ODS base metal. However, the TIG welded FeCrAl-ODS/SUS430 samples broke at a weld bond. X-ray CT scan analysis was performed for the weld bond, and the bonding strength was correlated with the X-ray CT results in order to assess the feasibility of those welding methods for ATF-ODS steel cladding.

Journal Articles

Overview of Japanese development of accident tolerant FeCrAl-ODS fuel claddings for BWRs

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

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 7 Pages, 2017/09

This paper will show the overview of current status of development of accident tolerant FeCrAl-ODS fuel claddings for BWRs (boiling water reactors) in the program sponsored and organized by the Ministry of Economy, Trade and Industry (METI) of Japan. This program is being carried out to create the technical basis for the practical use of the accident tolerant fuels and the other components in LWRs through multifaceted activities. In the development of FeCrAl-ODS fuel claddings both the experimental and the analytical studies have been performed. The acquisition and accumulation of key material properties of FeCrAl-ODS fuel claddings were conducted by using bar, sheet and tube shaped FeCrAl-ODS materials fabricated in this program to support the evaluations in the analytical studies. A neutron irradiation test was also started in the ORNL High Flux Isotope Reactor (HFIR) to examine the effect of neutron irradiation on the mechanical properties.

Journal Articles

Production of $$^{rm 95m}$$Tc for Compton camera imaging

Hatsukawa, Yuichi; Hashimoto, Kazuyuki; Tsukada, Kazuaki; Sato, Tetsuya; Asai, Masato; Toyoshima, Atsushi; Nagai, Yasuki; Tanimori, Toru*; Sonoda, Shinya*; Kabuki, Shigeto*; et al.

Journal of Radioanalytical and Nuclear Chemistry, 303(2), p.1283 - 1285, 2015/02

 Times Cited Count:2 Percentile:17.75(Chemistry, Analytical)

Technetium-99m ($$^{rm 99m}$$Tc) is used in radioactive medical diagonostic tests, for example as a radioactive tracer that medical equipment can detect in the human body. It is well suited to the role because it emits readily detectable 141 keV $$gamma$$ rays, and its half-life is 6.01 hours (meaning that about 94% of it decays to technetium-99 in 24 hours). There are at least 31 commonly used radiopharmaceuticals based on technetium-99m for imaging and functional studies of the brain, myocardium, thyroid, lungs, liver, gallbladder, kidneys, skeleton, blood, and tumors. Recent years, with the develop-ment of the Compton camera which can realize high position resolution, technetium isotopes emitting high energy $$gamma$$-rays are required. In this study, technetium-95m which emits some $$gamma$$ rays around 800 keV was produced by the $$^{95}$$Mo(p,n)$$^{rm 95m}$$Tc reaction.

Journal Articles

IFMIF/EVEDA lithium test loop; Design and fabrication technology of target assembly as a key component

Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakamura, Kazuyuki; Ida, Mizuho; Watanabe, Kazuyoshi; Kanemura, Takuji; Wakai, Eiichi; Horiike, Hiroshi*; Yamaoka, Nobuo*; et al.

Nuclear Fusion, 51(12), p.123008_1 - 123008_12, 2011/12

 Times Cited Count:37 Percentile:82.53(Physics, Fluids & Plasmas)

The Engineering Validation and Engineering Design Activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeded as one of the ITER Broader Approach (BA) activities. The EVEDA Li test loop (ELTL) is aimed at validating stability of the Li target and feasibility of a Li purification system as the key issues. In this paper, the design of the ELTL especially of a target assembly in which the Li target is produced by the contraction nozzle is presented.

Journal Articles

Status of Japanese design and validation activities of test facilities in IFMIF/EVEDA

Wakai, Eiichi; Kikuchi, Takayuki; Kogawara, Takafumi; Kimura, Haruyuki; Yokomine, Takehiko*; Kimura, Akihiko*; Nogami, Shuhei*; Kurishita, Hiroaki*; Saito, Masahiro*; Nishimura, Arata*; et al.

Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 6 Pages, 2011/03

Japanese activities of test facilities in IFMIF-EVEDA (International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities) project have three subjects of engineering design of post irradiation examination (PIE) facilities, small specimen test technique (SSTT), and engineering design of high flux test module (HFTM), and this paper is summarized about present status. Functional analysis and design of 2-D and 3-D models of PIE facility were performed. In HFTM, as materials of heater, W-3Re alloy and/or SiC/SiC composite were selected in the points of high temperature materials, fabrication technology and some suitable properties such as resistance of thermal shock, high temperature re-crystallization, ductility, resistance of irradiation degradation, and low-activation. In SSTT, a test machine of fracture toughness was designed and developed for small specimens with 10 mm square, and it had high accuracy controllability for stress and displacement.

Journal Articles

Preparation and evaluation of $$^{186/188}$$Re-labeled antibody (A7) for radioimmunotherapy with rhenium(I) tricarbonyl core as a chelate site

Ogawa, Kazuma*; Kawashima, Hidekazu*; Kinuya, Seigo*; Shiba, Kazuhiro*; Onoguchi, Masahisa*; Kimura, Hiroyuki*; Hashimoto, Kazuyuki; Odani, Akira*; Saji, Hideo*

Annals of Nuclear Medicine, 23(10), p.843 - 848, 2009/12

 Times Cited Count:9 Percentile:31.49(Radiology, Nuclear Medicine & Medical Imaging)

Rhenium is one of the most valuable elements for internal radiotherapy because $$^{186/188}$$Re have favorable physical characteristics. However, there are problems when proteins such as antibodies are used as carriers of $$^{186/188}$$Re. Labeling methods require the complicated processes. Therefore, we planned the preparation by a simple method and evaluation of a stable $$^{186/188}$$Re-labeled antibody. For this purpose, we selected $$^{186/188}$$Re(I) tricarbonyl complex as a chelating site. A7 was used as a model protein. $$^{186/188}$$Re-labeled A7 was prepared by directly reacting a $$^{186/188}$$Re(I) tricarbonyl precursor with A7. $$^{186/188}$$Re-(CO)$$_{3}$$-A7 were prepared with radiochemical yields of 23-28%. After purification, $$^{186/188}$$Re-(CO)$$_{3}$$-A7 showed a radiochemical purity of over 95%. In biodistribution experiments, $$^{186/188}$$Re-labeled A7 showed high uptakes in the tumor.

Journal Articles

Application of ITBL basic software for virtual organizations

Higuchi, Kenji; Otani, Takayuki; Hasegawa, Yukihiro*; Suzuki, Yoshio; Yamagishi, Nobuhiro*; Kimura, Kazuyuki*; Maesako, Hiroshi*; Fukuda, Masahiro; Yagawa, Genki

Keisan Kogaku Koenkai Rombunshu, 8(2), p.797 - 800, 2003/05

no abstracts in English

Journal Articles

Grid computing supporting system on ITBL project

Higuchi, Kenji; Imamura, Toshiyuki*; Suzuki, Yoshio; Shimizu, Futoshi; Machida, Masahiko; Otani, Takayuki; Hasegawa, Yukihiro*; Yamagishi, Nobuhiro*; Kimura, Kazuyuki*; Aoyagi, Tetsuo; et al.

Lecture Notes in Computer Science 2858, p.245 - 257, 2003/00

Prototype of the middleware for Grid project promoted by national institutes in Japan has been developed. Key technologies that are indispensable for construction of virtual organization were already implemented onto the prototype of middleware and examined in practical computer/network system from a view point of availability. In addition several kinds of scientific applications are being executed on the prototype system. It seems that successful result in the implementation of those technologies such as security infrastructure, component programming and collaborative visualization in practical computer/network systems means significant progress in Science Grid in Japan.

Journal Articles

Development of a virtual research environment in ITBL project

Higuchi, Kenji; Otani, Takayuki; Hasegawa, Yukihiro*; Suzuki, Yoshio; Yamagishi, Nobuhiro*; Kimura, Kazuyuki*; Aoyagi, Tetsuo; Nakajima, Norihiro; Fukuda, Masahiro; Imamura, Toshiyuki*; et al.

Proceedings of International Conference on Supercomputing in Nuclear Applications (SNA 2003) (CD-ROM), 11 Pages, 2003/00

An experimental application of Grid computing was executed in ITBL project promoted by six member institutes of MEXT. Key technologies that are indispensable for construction of virtual organization were implemented onto ITBL Middleware and examined in the experiment from a view point of availability. It seems that successful result in the implementation and examination of those technologies such as security infrastructure, component programming and collaborative visualization in practical computer/network systems means significant progress in Science Grid in Japan.

Journal Articles

Evaluation of communication performance among SCore cluster systems via VPN using MPI communication library, Stampi

Tsujita, Yuichi; Yamagishi, Nobuhiro*; Kimura, Kazuyuki*; Otani, Takayuki; Tsuruoka, Nobuhiko*; Fujita, Naoyuki*

Joho Shori Gakkai Kenkyu Hokoku 2002-HPC-92, p.7 - 12, 2002/10

SCore system has been developed to provide flat computing infrastructure for parallel computing without awareness of each compute host in a PC cluster system. An SCore cluster system can be handled as a single computer. MPICH-SCore, which is an MPI library in SCore, is not available across multiple SCore cluster systems as well as multiple platforms. We have implemented an MPI communication library, Stampi in SCore cluster system to enable MPI communication between SCore cluster systems and measured communication performance of the library using SCore cluster systems.

Oral presentation

Preparation of $$^{188}$$Re-labeled antibody (A7) by a simple method using rhenium(I) tricarbonyl complex

Ogawa, Kazuma*; Kawashima, Hidekazu*; Kinuya, Seigo*; Yoshimoto, Mitsuyoshi*; Shiba, Kazuhiro*; Kimura, Hiroyuki*; Hashimoto, Kazuyuki; Mori, Hirofumi*; Saji, Hideo*

no journal, , 

$$^{188}$$Re is one of the most useful radionuclides for internal radiotherapy. However, there is a problem when protein such as antibody is used as a carrier of $$^{188}$$Re. The labeling method using bifunctional chelating agents require the conjugation of $$^{188}$$Re-complex to protein after radiolabeling with the bifunctional chelating agent. Then, we planned the preparation of a stable $$^{188}$$Re-labeled protein by a simple method. A7 monoclonal antibody was labeled by reacting $$^{188}$$Re(I) tricarbonyl precursor with A7 directly. $$^{188}$$Re labeled A7 was prepared with radiochemical yield of 23%. After purification, $$^{188}$$Re labeled A7 showed radiochemical purity over 98%. After 24 hours of incubation, about 93% of $$^{188}$$Re-A7 remained intact, which indicates $$^{188}$$Re-A7 is stable in vitro. In biodistribution experiment, 11.2% of the injected dose/g of $$^{188}$$Re-A7 accumulated in the tumor at 24 hours postinjection, and tumor to blood ratio was over 1.0 at the same time.

Oral presentation

Synthesis and evaluation of $$^{186}$$Re-labeled biotin as a labeling agent for antibodies

Hirasawa, Makoto*; Kawashima, Hidekazu*; Ogawa, Kazuma*; Kimura, Hiroyuki*; Ono, Masahiro*; Hashimoto, Kazuyuki; Saji, Hideo*

no journal, , 

no abstracts in English

Oral presentation

Progress on engineering design and construction of IFMIF/EVEDA Li test loop

Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Iuchi, Hiroshi; Nakamura, Kazuyuki; Ida, Mizuho; Wakai, Eiichi; Watanabe, Kazuyoshi; Kanemura, Takuji; Horiike, Hiroshi*; et al.

no journal, , 

The International Fusion Materials Irradiation Facility (IFMIF) is a neutron source aimed at producing an intense high energy neutron flux for testing candidate materials to be used in the fusion demonstration reactor. Engineering Validation and Engineering Design Activities (EVEDA) on IFMIF started under Broader Approach. As a major Japanese activity for Li target tasks of EVEDA, EVEDA Li Test Loop is under construction. Feasibility of hydraulic stability of the Li target and purification systems of hot traps is major key issues to be validated. Toward the validation at the loop, laboratory-scale tests and design for diagnostics to the high-speed free-surface Li target and the hot traps to control nitrogen and hydrogen in Li are carried out along with the construction of the loop. Regarding to progress of the construction, all major components except a target assembly are installed in a mount of the loop. The construction is scheduled to be finished on Feb. 2011.

Oral presentation

Pretargeted radioimmunotherapy of tumor using a novel radiorhenium-labeled biotin derivative and streptavidin conjugated anti-cytokeratin 19 monoclonal antibody

Kawashima, Hidekazu*; Hirasawa, Makoto*; Kimura, Hiroyuki*; Ono, Masahiro*; Hashimoto, Kazuyuki; Saji, Hideo*

no journal, , 

no abstracts in English

Oral presentation

Production of $$^{95m}$$Tc for Compton camera imaging

Hatsukawa, Yuichi; Tsukada, Kazuaki; Hashimoto, Kazuyuki; Sato, Tetsuya; Asai, Masato; Toyoshima, Atsushi; Nagai, Yasuki; Tanimori, Toru*; Sonoda, Shinya*; Kabuki, Shigeto*; et al.

no journal, , 

In recent years, the Compton camera which is originally developed for the astrophysical studies was applied for medical diagnostic usage. For the Compton camera imaging require technetium isotopes emitting higher energy $$gamma$$-rays. Two Tc isotopes, $$^{95m}$$Tc (T$$_{1/2}$$ = 60 d; E$$gamma$$ = 204, 582 and 835 keV) and $$^{96}$$Tc(T$$_{1/2}$$ = 4.28 d, E$$gamma$$ = 778 and 812 keV) are candidates for Compton camera imaging. Compton camera imaging can realize high position resolution without collimator. Because of no collimator using, the Compton camera makes higher $$gamma$$-ray detection efficiency. Compared with SPECT with $$^{99m}$$Tc, the Compton camera imaging technique can be expected that radiation exposure deduce to 1/5-1/10. In this study, technetium-95m was produced by the $$^{95}$$Mo(p,n)$$^{95m}$$Tc reaction.

Oral presentation

R&D of advanced stainless steels for BWR fuel claddings, 7; Irradiation behavior evaluation

Yamashita, Shinichiro; Kondo, Keietsu; Aoki, So; Hashimoto, Naoyuki*; Ukai, Shigeharu*; Sakamoto, Kan*; Hirai, Mutsumi*; Kimura, Akihiko*; Kusagaya, Kazuyuki*

no journal, , 

As the lesson learned from the accident at the Fukushima Daiichi Nuclear Power Station, it is commonly recognized that development of the advanced fuel and core components with enhanced accident tolerance and high reliability is quite important for increasing safety of the existing Light Water Reactors (LWRs). FeCrAl-ODS steel is one of prospective candidate materials with enhanced accident tolerance and needs to be accumulated properly and efficiently fundamental and practical data for core and plant design of nuclear reactor. In this study, hardness measurement and microstructural observation for ion-irradiated FeCrAl-ODS steel were conducted in order to evaluate irradiation property in advance toward a research reactor irradiation test. The results indicated that steep irradiation hardening occurred at the initial stage of irradiation and also that nucleation and growth of irradiation defect cluster occurred at the higher dose than the irradiation hardening occurred.

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

29 (Records 1-20 displayed on this page)