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Do, Thi Mai Dung*; Sujatanond, S.*; Ogawa, Toru
Journal of Nuclear Science and Technology, 55(3), p.348 - 355, 2018/03
Times Cited Count:6 Percentile:52.79(Nuclear Science & Technology)In order to better understand the behavior of cesium in the severe accident of the LWR, the high-temperature chemistry of CsMoO in HO+H gas was studied. The pseudo-binary system, CsMoO-MoO, was thermochemically modeled with Redlich-Kister formulation to form a basis to analyze the high-temperature behavior of CsMoO. The model prediction was compared with the thermogravimetric measurements of CsMoO in dry and humid argon, which revealed that the mass-loss rate was enhanced in the humid atmosphere. Thermochemical model was further applied to predict the partitioning of cesium and molybdenum among gaseous species in the BWR core degradation condition typical of Short-Term Station Blackout.
Di Lemma, F. G.; Nakajima, Kunihisa; Yamashita, Shinichiro; Osaka, Masahiko
Journal of Nuclear Materials, 484, p.174 - 182, 2017/02
Times Cited Count:22 Percentile:90.44(Materials Science, Multidisciplinary)Chemisorption phenomena can affect fission products retention in the nuclear reactor vessel during a Severe Accident (SA). This paper will describe the influence of molybdenum contained in type 316 stainless steel (SS) on Cs chemisorption. Our experiments showed the formation of Cs-Mo compounds in addition to CsFeSiO, observed previously on SS304. The results of high temperature stability tests on the deposits are also presented. These tests aimed at simulating the revaporization of FP from structural materials during a SA. From our results, it can be inferred that Cs-Mo deposits may revaporize, contributing as a delayed source to the radioactive release.
Nakajima, Kunihisa; Nakazono, Yoshihisa; Arai, Yasuo
Recent Advances in Actinide Science, p.448 - 450, 2006/06
A pyrochemical process for the metallurgical treatment of the spent nuclear fuels contains the Cd-distillation step, where Pu is recovered as a residue. For understanding this Cd-ditillation behavior the samples of PuCd+PuCd and PuCd+PuCd were prepared and Knudsen-cell mass-spectrometric measurements were carried out to determine the vapour pressures of Cd(g) over these samples. Further,the thermodynamic quantities of PuCd and PuCd were evaluated from these vapour pressures.
Minato, Kazuo; Arai, Yasuo; Akabori, Mitsuo; Nakajima, Kunihisa
Proceedings of American Nuclear Society Conference "Nuclear Applications in the New Millennium" (AccApp-ADTTA '01) (CD-ROM), 6 Pages, 2002/00
In the Japan Atomic Energy Research Institute (JAERI), the concept of the transmutation of minor actinides (MA: Np, Am and Cm) with accelerator-driven systems (ADS) is being studied, where MA nitride is adopted as a fuel material of sub-critical core. The nitride fuel has been chosen as a candidate because of the possible mutual solubility among the actinide mononitrides and excellent thermal properties besides supporting hard neutron spectrum. Highly enriched N-15 would have to be used for the nitride fuel in order to prevent the formation of hazardous C-14. By applying pyrochemical process in the treatment of spent fuel, N-15 could be readily recovered and recycled. The present paper describes an overview of the research on the nitride fuel performed in JAERI. Fabrication experiments of actinide nitrides, measurements of vaporization behavior and thermal properties, and irradiation tests of actinide nitrides are summarized.
Shibazaki, Hiroaki*; Maruyama, Yu; Kudo, Tamotsu; Hashimoto, Kazuichiro*; Maeda, Akio*; Harada, Yuhei*; Hidaka, Akihide; Sugimoto, Jun
Nuclear Technology, 134(1), p.62 - 70, 2001/04
Times Cited Count:3 Percentile:27.1(Nuclear Science & Technology)no abstracts in English
Ogawa, Toru; Kobayashi, Fumiaki; Sato, Tadashi; R.G.Haire*
Journal of Alloys and Compounds, 271-273, p.347 - 354, 1998/00
Times Cited Count:16 Percentile:68.02(Chemistry, Physical)no abstracts in English
Ogawa, Toru
Journal of Nuclear Materials, 201, p.284 - 292, 1993/00
Times Cited Count:13 Percentile:76.59(Materials Science, Multidisciplinary)no abstracts in English
Kudo, Hiroshi; Wu, C. H.*
Journal of Nuclear Materials, 201, p.261 - 266, 1993/00
Times Cited Count:15 Percentile:79.5(Materials Science, Multidisciplinary)no abstracts in English
Maeda, Atsushi; ; Omichi, Toshihiko
Journal of Alloys and Compounds, 179, p.L21 - L24, 1992/00
Times Cited Count:17 Percentile:92.86(Chemistry, Physical)no abstracts in English
Uetsuka, Hiroshi;
JAERI-M 89-150, 27 Pages, 1989/10
no abstracts in English
*; ;
Int.J.Appl.Radiat.Isot., 32, p.595 - 599, 1981/00
Times Cited Count:3 Percentile:55.71(Nuclear Science & Technology)no abstracts in English
; ; ;
JAERI-M 7572, 20 Pages, 1978/03
no abstracts in English
Miwa, Shuhei; Shinada, Masanori; Osaka, Masahiko; Sugiyama, Tomoyuki; Maruyama, Yu
no journal, ,
In order to acquire the data on fission product chemical behavior during transport in a reactor for the improvement of source term evaluation method, we performed the chemical reaction tests of cesium (Cs) and iodine (I) deposits and boron oxide (BO) vapor/aerosol using the apparatus which can simulate temperature conditions of reactor coolant system under a sever accident. The volatile I compounds were formed by the reaction of BO vapor/aerosol and deposit, and significant amount of I was revaporized from the deposit.
Matsuura, Haruaki*; Kobayashi, Ami*; Miyoshi, Masahide*; Aihara, Haruka; Watanabe, So; Nomura, Kazunori
no journal, ,
Sato, Shin*; Ono, Hirokazu; Tanai, Kenji; Yamamoto, Shuichi*; Fukaya, Masaaki*; Shimura, Tomoyuki*; Niunoya, Sumio*
no journal, ,
Rizaal, M.; Miwa, Shuhei; Suzuki, Eriko; Imoto, Jumpei; Osaka, Masahiko; Goullo, M.*
no journal, ,