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JAEA Reports

Study on reactor core and fuel design of sodium cooled fast reactor, Mixed oxide fuel core; Results in JFY2005

Ogawa, Takashi; Sato, Isamu; Naganuma, Masayuki; Aida, Tatsuya*; Sugino, Kazuteru; Hayashi, Hideyuki

JAEA-Research 2006-061, 54 Pages, 2006/09

JAEA-Research-2006-061.pdf:3.86MB

Sodium cooled fast reactor with mixed oxide fueled core is one of the promising candidates in "Feasibility Study on Commercialized Fast Reactor Cycle System" in Japan. The results of the study on the reactor core and fuel design in the JFY2005 are reported. (1)Design studies of high internal conversion (HIC) type core: (i)Influence of TRU composition variation on the HIC type core and fuel designs was evaluated. (ii)In adopting PNC-FMS steel as alternative cladding material of ODS steel, influence to the reactor core and fuel design was evaluated for the large-scale HIC type core. (iii)Shielding property of the large-scale HIC type core was evaluated. (iv)Some measures to extend the lifetime of control rod were studied for the large-scale HIC type core. (2)Design study on high breeding performance: The core design corresponding to a requirement of high breeding performance was studied based on the large-scale compact type core designed in the JFY2004.

JAEA Reports

Improvements of the Control Rod Material for Long Lifetime by the High Power Millimeter-wave Ceramics Sintering Method

Idehara, Toshitaka*; Mitsudo, Seitaro*; Hoshizuki, Hisanori*; Ogawa, Isamu*; Shibahara, Itaru; Nishi, Hiroshi; Kitano, Akihiro; Ishibashi, Junichi

JNC TY4400 2003-005, 106 Pages, 2003/03

JNC-TY4400-2003-005.pdf:9.48MB

Boron Carbide B4C pellet is an important part of control rod used to control the reactivity of nuclear reactors. B4C pellet put in a nuclear reactor suffers heavy radiation damage and deformation, which result in a partial destruction and shorten the lifetime of B4C. It is important to improve the characteristics of the B4C pellets for extension of its lifetime. As the results, if the control rod without the shroud will be available, we can realize much simpler structure. In order to improve, the B4C pellet, which was sintered by the hot-press methods, we have re-sintered it by high power millimeter wave ceramics nano-indentation test. The increase of the plasticity is observed. The same improvement of plasticity was observed in alumina pellets that were sintered by millimeter wave sintering methods. Such results imply that the further improvement is expected, if the B4C pellet is sintered from powder specimen by the high power millimeter-wave sintering method. To simulate a partial destruction of B4C pellet under the thermal stress, preliminary internal heating experiments of B4C pellet are performed by using high power millimeter-wave. At the difference between internal and surface temperatures of 1000C, the partial destructions and small cracks are observed in B4C pellet. Thes may be a kind of model experiment for destruction of B4C pellet irradiated by neutrons.

Journal Articles

ZrC-coated particle fuel for high temperature gas-cooled reactors

Minato, Kazuo; Ogawa, Toru; Sawa, Kazuhiro; Sekino, Hajime; Koya, Toshio; Kitagawa, Isamu; Ishikawa, Akiyoshi; Tomita, Takeshi;

Proc. of the Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 8 Pages, 1999/00

no abstracts in English

Journal Articles

Fission product release from ZrC-coated fuel particles during post-irradiation heating at 1800 and 2000$$^{circ}$$C

Minato, Kazuo; Ogawa, Toru; Fukuda, Kosaku; Sekino, Hajime; Kitagawa, Isamu; Mita, Naoaki

Journal of Nuclear Materials, 249(2-3), p.142 - 149, 1997/00

 Times Cited Count:57 Percentile:95.97(Materials Science, Multidisciplinary)

no abstracts in English

Oral presentation

Design of gyrotron scattering diagnostics for density fluctuation measurement in JT-60

Ogawa, Isamu*; Idehara, Toshitaka*; Myodo, Masahiko*; Kamada, Masaki*; Hatae, Takaki; Shinohara, Koji; Oyama, Naoyuki; Hamamatsu, Kiyotaka

no journal, , 

no abstracts in English

Oral presentation

Porosity control of multifunction geopolymer foam

Ogawa, Toru; Utsumi, Taro*; Terasawa, Toshiharu*; Kudo, Isamu*; Suzuki, Tsuneo*; Nakayama, Tadachika*; Suematsu, Hisayuki*

no journal, , 

For the fuel debris management, we develop the preparation techniques for highly porous geopolymer, which would be used as the matrix of neutron absorber as well as hydrogen recombiner. By adding silicon powder to the raw materials, and hot water in mixing, we demonstrated the capability to prepare geopolymer with high fractions of open pores.

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