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Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.
Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07
This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.
Takemoto, Noriyuki; Itagaki, Wataru; Kimura, Nobuaki; Ishitsuka, Etsuo; Nakatsuka, Toru; Hori, Naohiko; Ooka, Makoto; Ito, Haruhiko
JAEA-Review 2013-063, 34 Pages, 2014/03
JAEA-Review-2013-063.pdf:8.46MB
Nuclear energy is important from a viewpoint of economy and energy security in Japan. However, the lack of nuclear engineers and scientists in future is concerned after the sever accident of TEPCO's Fukushima Daiichi Nuclear Power Station has occurred. Institute of National Colleges of Technology planned to carry out training programs for human resource development of nuclear energy field including on-site training in nuclear facilities. Oarai Research and Development Center in Japan Atomic Energy Agency cooperatively carried out an internship for nuclear disaster prevention and safety utilizing the nuclear facilities such as the JMTR. Thirty two students joined in total in the internship from FY 2011 to FY2013. In this paper, contents and results of the internship are reported.
Naito, Hiroyuki; Itagaki, Wataru; Okazaki, Yoshihiro; Imaizumi, Kazuyuki; Ito, Chikara; Nagai, Akinori; Kitamura, Ryoichi; Shamoto, Naoki*; Takeshima, Yoshiyuki*
JAEA-Technology 2012-009, 100 Pages, 2012/05
JAEA-Technology-2012-009.pdf:9.89MB
The radiation characteristics of image fiber and light guide fiber were evaluated to develop a high radiation resistant fiberscope for the fast reactor in-vessel observation. It is known that a pure silica core fiber has a high radiation resistance and radiation resistance is influenced with impurities in silica. Moreover it is necessary to change the clad material of the light guide fiber because that of the current light guide fiber is acrylate, which is weak against radiation. Hence the improved fibers consist of a pure silica core with 1,000 ppm OH and fluorine-doped silica clad. As a result of a 
irradiation test, we confirm that OH inhibits the generation of the precursor by irradiation. About the clad material, we confirmed that the transmission loss of the fluorine-doped silica clad fiber is smaller than that of the acrylate clad fiber. About the mechanical strength of a fiber, we confirmed that there is no weakening the strength of the fiber and no exfoliation of the coating from the glass. In this study, we discovered the fiber which consists of a pure silica core with 1,000 ppm OH and fluorine-doped silica clad has a high radiation resistance and it is possible to observe using this fiber under the 200 
C after 5
10
Gy irradiation.
Nakamura, Kinya*; Ogata, Takanari*; Kikuchi, Hironobu; Iwai, Takashi; Nakajima, Kunihisa; Kato, Tetsuya*; Arai, Yasuo; Uozumi, Koichi*; Hijikata, Takatoshi*; Koyama, Tadafumi*; et al.
Nihon Genshiryoku Gakkai Wabun Rombunshi, 10(4), p.245 - 256, 2011/12
Sodium-bonded metallic fuel elements were fabricated for the first time in Japan for the irradiation test in the experimental fast test reactor JOYO. U-20Pu-10Zr fuel slugs of 200 mm in length and approximately 5 mm in diameter were fabricated in a small-scale injection casting furnace. Each fuel slug was loaded into the ferritic martenstic stainless steel (PNC-FMS) cladding tube with the sodium thermal bond, thermal insulator and reflector in a helium gas atmosphere glove box. After top-end plug welding to the cladding tube and heat treatment of the welding area, each fuel element was subjected to the sodium bonding process. After the inspection such as element length, gas plenum length and helium-leak tightness, six metallic fuel elements are transported to the JOYO site for the coming irradiation test.
Nakamura, Kinya*; Ogata, Takanari*; Kikuchi, Hironobu; Iwai, Takashi; Nakajima, Kunihisa; Kato, Tetsuya*; Arai, Yasuo; Koyama, Tadafumi*; Itagaki, Wataru; Soga, Tomonori; et al.
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 8 Pages, 2011/12
CRIEPI and JAEA have fabricated sodium-bonded metallic fuel elements for the first time in Japan as a collaborative research, for use in the irradiation test at the experimental fast test reactor Joyo. The irradiation test aims to assess the irradiation behavior of the fuel and the internal wastage of the stainless-steel cladding by rare-earth fission products at a maximum cladding temperature above 873 K. U-20 wt% Pu-10 wt% Zr alloy fuel slugs of 200 mm length were fabricated in an injection-casting furnace using U metal, U-Pu alloy and Zr metal. Two types of fuel slug were fabricated, i.e., 5.05 mm and 4.95 mm in diameter, and loaded into a ferritic-martensitic stainless-steel cladding tubes, respectively. After top-end-plug welding to the cladding tube, each fuel element was subjected to sodium bonding to fill the annular gap between the fuel slug and the cladding with melted sodium. The fabrication results indicated that the characteristics of the fuel elements were within the required specifications.
Itagaki, Wataru; Saito, Takakazu; Imaizumi, Kazuyuki; Nagai, Akinori; Aoyama, Takafumi; Maeda, Yukimoto
Dai-14-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.435 - 438, 2009/06
no abstracts in English
Itagaki, Wataru; Sekine, Takashi; Imaizumi, Kazuyuki; Maeda, Shigetaka; Ashida, Takashi; Takamatsu, Misao; Nagai, Akinori; Maeda, Yukimoto
Proceedings of 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA 2009) (USB Flash Drive), 7 Pages, 2009/06
no abstracts in English
Maeda, Shigetaka; Soga, Tomonori; Itagaki, Wataru; Sekine, Takashi; Aoyama, Takafumi
no journal, ,
High linear power irradiation test and post irradiation experiment is carried out using low-density MOX fuel which contains Am in experimental fast reactor Joyo in order to confirm thermal performance of the fuel for fast reactor which contains minor actinides such as americium. Irradiation test and irradiation condition evaluation are reported. In the irradiation test, Maximum reactor thermal output 124.8MWt was achieved by the rise to power pattern for simulating over power right after the preconditioning. As an irradiation condition evaluation, the analysis simulated in detail to the structure of the fuel pellet using Monte Carlo calculation code MCNP was carried out, and line heat rate of the test fuel pin was obtained. Largest line output of the each element which evaluated the calculated value of MCNP by correcting (about C/E=0.98) at combustion rate measured value by the Nd method of post irradiation experiment, was 463-476W/cm at 124.8MWt.
Abe, Kazuyuki; Itagaki, Wataru; Maeda, Koji; Nagamine, Tsuyoshi; Nakamura, Yasuo
no journal, ,
To decrease the irradiation bowing of JOYO inner reflector, the improvement of an internal structure and Corotation were executed, and the effect was confirmed by the post irradiation examination.
Itagaki, Wataru; Soga, Tomonori; Baba, Shinichi; Morozumi, Katsufumi; Aoyama, Takafumi; Miyake, Osamu
no journal, ,
no abstracts in English
Itagaki, Wataru; Ito, Chikara; Maeda, Shigetaka; Yamamoto, Masaya
no journal, ,
no abstracts in English
Soga, Tomonori; Itagaki, Wataru; Noguchi, Koichi
no journal, ,
For the various irradiation tests, the compartment type rigs that set the coolant temperature individually, and the capsule type rig that can irradiate the advanced fuel pins, were developed in Joyo. Moreover, the online irradiation rigs which can measure or control the temperature with high accuracy had been developed and utilized in Joyo. These rigs contribute the basic research in the irradiation effect on material, and the research for the LWR or the fusion reactor. In addition, the high temperature irradiation test device, and the device which has function of the neutron energy spectrum tailoring will be prepared to expand the range of the irradiation condition. In PIE facilities that are adjacent to Joyo, parts of irradiation rigs or samples can be exchanged after irradiation. Then re-assembled rig can be re-loaded to Joyo. This technique enables to obtain the data on the way to the target burn-up or fluence, and to conduct the longer irradiation test than the lifetime of rigs.
Sano, Aaru; Maeda, Shigetaka; Itagaki, Wataru; Sasaki, Shinji; Sasaki, Yuto*; Takaki, Naoyuki*
no journal, ,
Ac-225 is attracting attention as an alpha emitting medical radioisotope. Since its demand is expected to increase, domestic production of Ac-225 is required from the viewpoint of medical research and economic security of Japan. To establish the technical bases for the Ac-225 production, JAEA has evaluated the radioactivity can be produced in the experimental fast reactor Joyo and designed the concept that upgrades the existing facilities for transporting the irradiated target from Joyo to a neighboring PIE facility rapidly. This study has revealed that Joyo can sufficiently produce Ac-225 as a raw material for pharmaceuticals.
Itagaki, Wataru; Soga, Tomonori; Yamamoto, Masaya; Sekine, Takashi
no journal, ,
no abstracts in English
Itagaki, Wataru; Soga, Tomonori; Aoyama, Takafumi; Ogata, Takanari*; Nakamura, Kinya*
no journal, ,
no abstracts in English
Nakamura, Kinya*; Ogata, Takanari*; Nakajima, Kunihisa; Kato, Tetsuya*; Iwai, Takashi; Arai, Yasuo; Koyama, Tadafumi*; Itagaki, Wataru; Soga, Tomonori
no journal, ,
Irradiation test of metallic fuel at fast test reactor JOYO is planned. By using techniques of casting, fabrication, analysis and inspection, metallic fuel elements were made for the first time in Japan. In this paper, results of fabrication of U-Pu-Zr alloy fuel slug by emit casting method. Using U metal, U-Pu alloy metal and Zr metal as raw materials, fuel slugs were fabricated by emit casting apparatus in argon gas atmosphere glove box. By inspection, it was confirmed that the specifications were satisfied.
Aoyama, Takafumi; Itagaki, Wataru
no journal, ,
no abstracts in English
Ogata, Takanari*; Nakamura, Kinya*; Itagaki, Wataru; Soga, Tomonori; Aoyama, Takafumi; Okubo, Tsutomu
no journal, ,
no abstracts in English
Nakamura, Kinya*; Kikuchi, Hironobu; Ogata, Takanari*; Iwai, Takashi; Arai, Yasuo; Uozumi, Koichi*; Hijikata, Takatoshi*; Koyama, Tadafumi*; Itagaki, Wataru; Soga, Tomonori
no journal, ,
Irradiation test of metallic fuel at fast test reactor JOYO is planned. By using techniques of casting, fabrication, analysis and inspection, metallic fuel elements were made for the first time in Japan. In this paper, fabrication technique of metallic fuel elements is reported. After filling up thermal bond (Na), a reflector element, a thermal shelter element and a fuel slug, the upper plug was welded. Sodium bonding treatment was carried out by vibrating the fuel element under heating. By inspection, it was confirmed that the specifications were satisfied.
