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Kurabayashi, Kazuaki; Kawaguchi, Yoshihito; Takaya, Akikazu; Morimoto, Kazuyuki; Kanamori, Sadamu; Omori, Eiichi
no journal, ,
Plutonium product recovered from Fugen MOX type B spent fuel is measured temperature at Tokai Reprocessing Plant. And we studied difference between estimated by ORIGEN and analytical value of relative promotion on Pu, moreover, we studied calculation model because of the difference between initial evaluation and temperature of Pu product.
Hoshi, Takahiro; Kawaguchi, Yoshihito; Kitao, Takahiko; Oyama, Koichi; Morimoto, Kazuyuki; Kanamori, Sadamu; Omori, Eiichi
no journal, ,
For reprocessing nuclear spent fuel, in future, used for plutonium-thermal and fast-breeding reactor, density of DBP in extraction solvent on reprocessing Fugen MOX Type B fuel was measured. And we formulated an equation for increased density of DBP to estimate density of DBP in extraction cycle.
Tanabe, Fumiya
no journal, ,
JCO criticality accident occurred by utilizing a precipitation tank without favorite geometry instead of the pure uranyl nitrate solution (UNH) tank with favorite geometry in homogenizing large amount of product UNH, which is much more than the criticality mass limit. One of causes of the accident is in changing the procedure without asking permission from the superior of the working team (special crew). It was resulted from the long experience in the JCO's improvement proposal campaign, in which proposals which had already been implemented were strongly recommended and highly evaluated, and then changing procedures without superior's permission had become common.
Chiba, Satoshi; Iwamoto, Osamu; Nakagawa, Tsuneo; Chiba, Go; Okumura, Keisuke
no journal, ,
By using integral data for fast reactor systems, adjustment of nuclear model parameters such as optical model potential and deformation parameters and microscopic nuclear data was achieved.
Onuki, Akira; Nakagawa, Masaki*; Nagayoshi, Takuji*; Tamai, Hidesada; Katono, Kenichi*
no journal, ,
no abstracts in English
Nagayoshi, Takuji*; Tamai, Hidesada; Katono, Kenichi*; Nakagawa, Masaki*; Onuki, Akira
no journal, ,
no abstracts in English
Tamai, Hidesada; Nagayoshi, Takuji*; Katono, Kenichi*; Nakagawa, Masaki*; Onuki, Akira
no journal, ,
no abstracts in English
Ito, Kazuhiro; Yamamoto, Masaya; Maeda, Koji; Akasaka, Naoaki; Harada, Akio; Konashi, Kenji*
no journal, ,
As part of "Development of Hydride Neutron Absorber for Fast Reactor", a series of neutron irradiation experiment with in HfH, (Gd+ZR)H and stainless steel specimens was performed in experimental fast reactor Joyo. Here, the stainless steel specimens were coated by oxide film to simulate a cladding tube. In this report, the irradiation examination plan and a result were summarized.
activity on the dissolution rate of compacted montmorilloniteKadowaki, Mitsushi; Yamaguchi, Tetsuji; Mukai, Masayuki; Iida, Yoshihisa; Tanaka, Tadao; Nakayama, Shinichi
no journal, ,
no abstracts in English
Arai, Yoichi; Ogino, Hideki; Onose, Tsutomu*; Koizumi, Satoshi*; Fujisaku, Kazuhiko*; Yokoyama, Yoshitomo*
no journal, ,
no abstracts in English
, U
, UO
, and UO
in molten LiCl-RbCl eutecticNagai, Takayuki; Uehara, Akihiro*; Fujii, Toshiyuki*; Yamana, Hajimu*; Shirai, Osamu*; Sato, Nobuaki*
no journal, ,
no abstracts in English
Shikaze, Yoshiaki; Tanimura, Yoshihiko; Saegusa, Jun; Tsutsumi, Masahiro; Yoshizawa, Michio
no journal, ,
no abstracts in English
Kaji, Naoya; Nakahara, Masaumi; Nakamura, Kazuhito; Shibata, Atsuhiro; Tomita, Yutaka; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu
no journal, ,
Solubility obtained from the latest crystallization tests using irradiated fuel and the tests implemented before using U or Pu/U are compared with the data showed by Hart. Based on the result, availability of the data to estimate crystallization ratio is considered.
Aoyama, Yoshio; Yamaguchi, Hiromi; Sakakibara, Tetsuro; Hanamoto, Yukio; Murata, Minoru*; Sasaki, Nao*; Nishikawa, Tsutomu*; Taniguchi, Shoji*; Shimazaki, Shinichi*; Park, J.*; et al.
no journal, ,
no abstracts in English
Chiba, Go; Okumura, Keisuke
no journal, ,
In order to increase an accuracy of reactor calculations with multi-group libraries, (a) nuclide- and energy-group-dependent Bell factor is adopted, (b) multiple R-parameter to consider resonance interference with other nuclides is adopted and (c) Bell factor is adjusted to cancel out errors caused by coarse group structure.
Aoyama, Yoshio; Yamaguchi, Hiromi; Sakakibara, Tetsuro; Hanamoto, Yukio; Murata, Minoru*; Sasaki, Nao*; Nishikawa, Tsutomu*; Taniguchi, Shoji*; Shimazaki, Shinichi*; Park, J.*; et al.
no journal, ,
no abstracts in English
and NaCl concentrations on sorption distribution coefficients of hydrogen selenide anion (HSe) on a sandy mudstoneKimura, Yuichiro; Yamaguchi, Tetsuji; Iida, Yoshihisa; Tanaka, Tadao; Nakayama, Shinichi
no journal, ,
no abstracts in English
Aoyama, Yoshio; Yamaguchi, Hiromi; Sakakibara, Tetsuro; Hanamoto, Yukio; Murata, Minoru*; Sasaki, Nao*; Nishikawa, Tsutomu*; Taniguchi, Shoji*; Shimazaki, Shinichi*; Park, J.*; et al.
no journal, ,
no abstracts in English
Asakura, Toshihide; Imaizumi, Hirobumi; Sasaki, Yuji; Kitatsuji, Yoshihiro; Morita, Yasuji; Kimura, Takaumi
no journal, ,
Total TRU separation technology using diglycolamide as an extraction solvent has been developed to apply it to the MA separation process of the spent FBR fuel reprocessing, etc. Separation tests were performed using Mixer-settlers. 1 M (mol dm
) nitric acid solution containing Nd, Sr, Zr, Pd, HO and EDTA was used as the feed, and 0.1 M tetradodecyl diglycolamide / docecane was used as the extraction solvent. Only Nd was used to represent the trivalent cations such as Am, Cm and rare earthes. As the results, Nd was extracted from the feed and Sr was separated from Nd, highly effectively. Almost all of Zr and Pd were not extracted and transferred to raffinate, 3 % of Zr and 0.4 % of Pd, however, were transferred to the Nd product.
Yamane, Yuichi
no journal, ,
In the criticality accident of nuclear solution fuel for which reactivity temperature coefficient was zero, the dependency of the first peak power on its reciprocal period was investigated and it was found that the first peak power was proportional to the reciprocal period and showed large value depending on the difference between the initial and boiling temperature under the condition in which radiolytic dissolution gas and boiling gas void be effective right after the beginning of boiling of the solution.