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pebble bed from the core of JMTRIkeshima, Yoshiaki; Ishida, Takuya*; Tsuchiya, Kunihiko; Tomita, Kenji; Ebisawa, Hiroyuki; Magome, Hirokatsu; Nakamichi, Masaru*; Kitajima, Toshio; Kawamura, Hiroshi
JAERI-Tech 2005-005, 37 Pages, 2005/02
JAERI-Tech-2005-005.pdf:7.59MB
no abstracts in English
Hidaka, Akihide
Nihon Genshiryoku Gakkai-Shi, 45(8), p.493 - 496, 2003/08
In order to investigate the radionuclides release from irradiated fuel under severe accident conditions of LWR, VEGA experimental facility that realizes the highest temperature and pressure conditions was designed and constructed at JAERI. The effect of ambient pressure on radionuclides release was uniquely quantified by using this facility. A model that explains the observed pressure effect was also proposed based on the experimental results. For this effort, the atomic energy society of Japan gave us the preeminent monograph award in FY 2002. This paper describes my encounter with the research awarded this time, fascination of this research, hard-worked points, future plans and so on.
fuel in helium atmosphere under elevated pressure of 1.0MPa at temperature up to 2,773KHidaka, Akihide; Kudo, Tamotsu; Nakamura, Takehiko; Uetsuka, Hiroshi
Journal of Nuclear Science and Technology, 39(7), p.759 - 770, 2002/07
Times Cited Count：6 Percentile：39.48(Nuclear Science & Technology)no abstracts in English
Osaka, Masahiko; Koyama, Shinichi; Mitsugashira, Toshiaki; Morozumi, Katsufumi; Namekawa, Takashi
JNC TN9400 2000-058, 49 Pages, 2000/04
JNC-TN9400-2000-058.pdf:1.22MB
The analytical technique for Cm contained in a MOX FUEL was developed and analysis of Cm contained in irradiated fuel of experimental fast reactor "JOYO" was carried out, to contribute to evaluation of transmutation characteristics of MA nuclide in the fast reactor. The procedure of ion-exchange separation of Cm with nitric acid-methanol mixed media essential for the isotopic analysis in irradiated MOX fuel was adopted considering for being rapid and easy. The fundamental test to grasp separation characteristics of this procedure, such as Cm elution position and separation capacity between Cm and Am or Eu, was carried out. ln applying this procedure to the analysis of Cm contained in actual specimen, separation condition was evaluated and optimized, and the procedure consist of impurity removal and Am removal process was devised. This procedure resulted in high recovery rate of Cm and high removal rate of Am and impurity which becomes a problem in sample handling and mass-spectrometry such as Eu and Cs. The Cm separation test from irradiated MOX fuel was carried out using this technique, and Cm isotopic ratio analysis was enabled. The analytical technique for Cm contained in irradiated MOX fuel was established using the procedure of ion-exchange separation with nitric acid-methanol mixed media. The analysis of Cm contained in irradiated MOX fuel of experimental fast reactor "Joyo" was carried out. As a result, it was revealed from measured data that Cm content rate was 1.4
4.0
lO
atom%, small amount of 
Cm was generated and Cm isotopic ratio was constant above burn-up 60GWd/t.
; Koyama, Tomozo; Funasaka, Hideyuki
JNC TN8400 2000-016, 188 Pages, 2000/03
We summarized the conditions and results of all dissolution experiments (bench scale experiments (dissolution of sheared fuel pins) and beaker scale experiments (dissolution of a few sheared fuels pieces) of the irradiated fast reactor fuels, which were carried out in the Chemical Processing Facility (CPF). The fabrication and irradiation conditions of the dissolved fuels were also put in order.
; Koyama, Tomozo; Funasaka, Hideyuki
JNC TN8400 2000-014, 78 Pages, 2000/03
JNC-TN8400-2000-014.pdf:2.13MB
We investigated the factors which affected the dissolution of U and Pu to the nitric acid solution with the fragmentation model, which was based on the results of dissolution experiments for the irradiated fast reactor fuels in the Chemical Processing Facility(CPF). The equation that gave the fuel dissolution rate was estimated with the condition of fabrication (Pu ratio (Pu/(U+Pu))), irradiation (burn-up) and dissolution (nitric acid concentration, solution temperature and U+Pu concentration) by evaluating these effects quantitatively. We also investigated the effects of fuel volume ratio to the solution in the dissolver, burn-up and flouring ratio of the fuel on the f-value (the parameter which shows the diffusion and osmosis of nitric acid to the fuel) in the fragmentation model. It was confirmed that the fuel dissolution rate calculated with this equation had better agreement with the results of dissolution experiments for the irradiated fast reactor fuels in the CPF than that estimated with the surface area model. In addition, the efficiency of this equation was recognized for the dissolution of unirradiated U pellet and high Pu enriched MOX fuel. It was shown that the dissolution rate of the fuel slowed down at the condition of the high U-Pu concentration dissolution by the calculation of the dissolution behavior with this equation. The dissolution of the fuel can be improved by increasing the nitric acid concentration and temperature, but from the viewpoint of lowering the corrosion of the dissolver materials, it is desirable that the f-value is increased by optimizing the condition of shearing and stirring for the improvement of dissolution.
Yasuda, Ryo; Nishi, Masahiro; Nakata, Masahito; Matsubayashi, Masahito
JAERI-Tech 2000-030, p.20 - 0, 2000/03
no abstracts in English
Sakai, Akihiro; Yoshimori, Michiro; Abe, Masayoshi
JAERI-Tech 2000-012, p.107 - 0, 2000/03
JAERI-Tech-2000-012.pdf:6.47MB
no abstracts in English
Hidaka, Akihide; Nakamura, Takehiko; Kudo, Tamotsu
Genshiryoku eye, 46(3), p.79 - 83, 2000/03
no abstracts in English
Hidaka, Akihide; Nakamura, Takehiko; Nishino, Yasuharu; Kanazawa, Hiroyuki; Hashimoto, Kazuichiro; Harada, Yuhei; Kudo, Tamotsu; Uetsuka, Hiroshi; Sugimoto, Jun
JAERI-Conf 99-005, p.211 - 218, 1999/07
no abstracts in English
*; Ishijima, Kiyomi; Yamahara, Takeshi
JAERI-Data/Code 98-002, 24 Pages, 1998/02
JAERI-Data-Code-98-002.pdf:1.02MB
no abstracts in English
Nakamura, Takehiko; *; Sasajima, Hideo; Fuketa, Toyoshi; *
JAERI-Research 96-060, 110 Pages, 1996/11
JAERI-Research-96-060.pdf:2.74MB
no abstracts in English
Yumoto, Ryozo*; Yokochi, Yoji*; Koizumi, Masumichi*; Seki, Sadao*
PNC TJ9409 96-002, 93 Pages, 1996/03
The state of development of pyrometallurgical partitioning and extracting technology of irradiated fuel is investigated. Also in case of perfoming the test at O-arai engineering center, the contents of the test, equipments, structure and arragement of cells that equipments are installed, are studied. The purpose of the test is to confirm the realization of the process and behavior of FP and TRU elements, and off-gass that cannot be made dear by cold test. In this study it is assumed that 100g monju fuel (94,000MWd/t B.U, cooled for 550 days) per batch is treated. Four processes are picked up except for pin sectioning and powdering, as important subjects. They are as follows. (1)reduction of oxide fuel (2)electrorefining (3)cathode processing (4)extraction of TRU elements. And the outline of the test, blocked flow chart and the outline of equipment are clarified. And the outline of chart is drawn. Moreover, the specification of analitical equipments which are necessary to analyze the product is shown. From spent chloride, TRU and a part of FP elements are extracted and they are recycled for electrorefining and so on. The salt-waste including residual FP elements is kept in a receptacle after being absorbed into Zeorite and soldified. As the disposition of these tests, modified test cell in the existing FMF, modified concrete cell in AGF, new cell at B2F in the existing FMF and new cell at second auxiliary room in FMF extension are studied. As result of considering the disposition for equipment, the difficulty of reconstucting new cell including of equipments, method of mentenance, and equipments of ventilazion (Ar circumstance) including of management of off gas, and the plan of disposition, it is concluded that constructing iron cell into the second auxiliary room of FMF extension is best, because it is easy to construct safely, and the occurance of radioactive waste and the influence to other tests is little, and it is possible to examine more efficiently.
Sasajima, Hideo; Fuketa, Toyoshi; *; Ishijima, Kiyomi; ; Yamahara, Takeshi; ; Ito, Tadaharu
JAERI-Research 95-087, 179 Pages, 1995/12
JAERI-Research-95-087.pdf:12.06MB
no abstracts in English
; Sakai, Toshiyuki*; Sanyoshi, Hirotaka; Iwasaki, Isao*; Kuribayashi, Masakazu*;
PNC TN8410 95-056, 65 Pages, 1995/03
None
Katanishi, Shoji; Ishijima, Kiyomi; ; Kikuchi, Teruo;
JAERI-Research 94-039, 54 Pages, 1994/11
JAERI-Research-94-039.pdf:5.2MB
no abstracts in English
Sasajima, Hideo
JAERI-M 90-029, 12 Pages, 1990/02
no abstracts in English
; ; Matsuura, Shojiro
JAERI-M 8599, 13 Pages, 1979/11
no abstracts in English
JAERI-M 5878, 124 Pages, 1974/10
no abstracts in English
*
Uraga Juko Giho, p.0 - 0, 1963/03
no abstracts in English
