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JAEA Reports

Internship using nuclear facilities in Oarai Research and Development Center

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.

JAEA Reports

Inspection and repair techniques in the reactor vessel of the experimental fast reactor Joyo; Development of a high radiation resistance fiberscope (Joint research)

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 $$gamma$$ irradiation test, we confirm that OH inhibits the generation of the precursor by $$gamma$$ 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 $$^{circ}$$C after 5$$times$$10$$^{5}$$ Gy irradiation.

Journal Articles

Fabrication of U-Pu-Zr metallic fuel elements for the irradiation test at experimental fast test reactor Joyo

Nakamura, Kinya*; Ogata, Takanari*; Kikuchi, Hironobu; Iwai, Takashi; Nakajima, Kunihisa; Kato, Tetsuya*; Arai, Yasuo; Uozumi, Koichi*; Hijikata, Takatoshi*; Koyama, Tadafumi*; et al.

Nippon 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.

Journal Articles

Fabrication of U-Pu-Zr metallic fuel elements for irradiation test at Joyo

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.

Journal Articles

Inspection techniques in reactor vessel of sodium cooled fast reactor

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

Journal Articles

In-vessel visual inspection of experimental fast reactor Joyo

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

Oral presentation

Development of techniques for minor actinides transmutation using fast reactor, 2; Irradiation test for MA containing fuel in experimental fast reactor JOYO

Takamatsu, Misao; Itagaki, Wataru; Soga, Tomonori; Sekine, Takashi; Aoyama, Takafumi

no journal, , 

no abstracts in English

Oral presentation

Improvement of irradiation test efficiency in "JOYO" by recycling rigs (shuttle irradiation technology), 1; The Plan and the achievement

Itagaki, Wataru; Kitamura, Ryoichi; Yamamoto, Masaya; Abe, Kazuyuki

no journal, , 

no abstracts in English

Oral presentation

Irradiation tests in the experimental fast reactor JOYO

Itagaki, Wataru; Soga, Tomonori; Yamamoto, Masaya; Sekine, Takashi

no journal, , 

no abstracts in English

Oral presentation

Post-irradiation examination results for improved JOYO inner reflector; Confirmation of effect of Corotation

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.

Oral presentation

Current status of Joyo

Itagaki, Wataru; Aoyama, Takafumi

no journal, , 

no abstracts in English

Oral presentation

Visual inspection and handing of obstacle in the Joyo in-vessel storage rack

Itagaki, Wataru; Aoyama, Takafumi

no journal, , 

no abstracts in English

Oral presentation

Current status & summary of irradiation tests in Joyo

Aoyama, Takafumi; Itagaki, Wataru

no journal, , 

no abstracts in English

Oral presentation

Development of high temperature irradiation techniques using fast reactor, 2; Development of alloy melting type temperature monitor

Itagaki, Wataru; Soga, Tomonori; Baba, Shinichi; Morozumi, Katsufumi; Aoyama, Takafumi; Miyake, Osamu

no journal, , 

no abstracts in English

Oral presentation

Inspection techniques in reactor vessel of sodium cooled fast reactor

Itagaki, Wataru

no journal, , 

no abstracts in English

Oral presentation

High linear power irradiation test with Am-MOX fuels, 3; Irradiation test in Joyo and linear heat rate evaluation

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.

Oral presentation

The Evaluation techniques for irradiation test conditions in Joyo

Itagaki, Wataru; Ito, Chikara; Maeda, Shigetaka; Yamamoto, Masaya

no journal, , 

no abstracts in English

Oral presentation

The Development of irradiation test rigs in the experimental fast reactor Joyo

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.

Oral presentation

Development of radiation resistant fiberscope for inspection in reactor vessel of fast reactor, 2

Naito, Hiroyuki; Itagaki, Wataru; Ito, Chikara; Okazaki, Yoshihiro; Nagai, Akinori; Shamoto, Naoki*; Takeshima, Yoshiyuki*

no journal, , 

no abstracts in English

Oral presentation

Fabrication of metallic fuel for irradiation test at JOYO, 4; Fabrication of metallic fuel elements

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.

35 (Records 1-20 displayed on this page)