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Fujita, Reiko*; Nakamura, Hitoshi*; Mizuguchi, Koji*; Utsunomiya, Kazuhiro*; Amamoto, Ippei
Proceedings of 2008 Joint Symposium on Molten Salts (USB Flash Drive), p.886 - 891, 2008/10
Pyrochemical treatment in molten salts is a promising process for decontamination of radioactive wastes without producing large amounts of secondary waste. In this report, the fundamental experiment was carried out to treat the wastes which had complicated shapes such as Magnoxend corps, metallic waste contaminated by uranium, spent chemical trap fillers and spent Zircaloy channel boxs from BWR and acquired good results.
; Utsunomiya, Kazuhiro*; *; *; Fujita, Reiko*
JNC TJ6400 2002-006, 173 Pages, 2003/03
JNC-TJ6400-2002-006.pdf:4.72MB
None
*; Fujita, Reiko*; Yahata, Hidetsugu*; *; Utsunomiya, Kazuhiro*
JNC TJ8400 2001-029, 52 Pages, 2001/01
JNC-TJ8400-2001-029.pdf:3.96MB
Pyrochemical reprocessing is one of a successful candidate of good economy for spent fuel reprocessing. Metallic fuel reprocessing process based on Argonne National Laboratory technology needs a reduction process from oxide fuel to metallic fuel to be applied to oxide fuel reprocessing. This study has examined the reduction process using metallic Li as a reducing agent for UO
which is comparatively estimated with the results of U
O
examined last year after investigating the material of mesh basket with literature. The mesh basket made of Ti and W for oxide container, which are selected by investigating the material of mesh basket with literature, were both broken during reduction. However, the mesh basket made of several layers of stainless steel was not broken at the same reduction condition. The reduction ratio of UO was estimated to be about 80-100% by a gas bullet method or an acidic pretreatment method. The influence of simulated fission products (FPs) on the reduction ratio of UO was nothing, however the reduction products were mixed with the simulated FPs. A further study such as investigating the behavior of FPs in the Li reduction conditions and establishing the separation process of FPs from the reduction products of UO is necessary.
Fujita, Reiko*; *; Kondo, Naruhito*; Utsunomiya, Kazuhiro*
JNC TJ8420 2000-004, 41 Pages, 2000/03
JNC-TJ8420-2000-004.pdf:5.08MB
no abstracts in English
Fujita, Reiko*; Yahata, Hidetsugu*; Kondo, Naruhito*; Utsunomiya, Kazuhiro*
JNC TJ8400 2000-066, 45 Pages, 2000/03
no abstracts in English
*; Utsunomiya, Kazuhiro*; *
PNC TN9410 87-068, 106 Pages, 1987/03
In the LMFBR "Monju" a good heat insulator, perlite concrete, is to be used between the inner concrete structures and the liner plate against the rapid-temperature increase of concrete structures when the hypothetical coolant leak accidents are occured. The purpose of present test is to confirm its safety even in the accidents. The tests were conducted in various conditions, which ofcource include "Monju" design conditions (at 450
C, 
0.25 kcal/mhC) and it was confirmed that the design conditions of "Monju" were satisfied even in any kind of situations. The main results of tests are as follows. (1) The design conditions of thermal conductivity of "Monju" perlite concrete were satisfied even in any test conditions. (2) Temperature dependence of its thermal conductivity was mainly dominated by that of water included in the perlite concrete. (3) The characteristics of its thermal conductivity could well explained by using its porosity.
Amamoto, Ippei; Fukushima, Mineo; Matsuyama, Kanae*; Okita, Takeshi*; Miyamoto, Shinya*; Utsunomiya, Kazuhiro*; Yano, Tetsuji*
no journal, ,
no abstracts in English
Amamoto, Ippei; Fukushima, Mineo; Matsuyama, Kanae*; Okita, Takeshi*; Miyamoto, Shinya*; Utsunomiya, Kazuhiro*; Yano, Tetsuji*
no journal, ,
no abstracts in English