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Soler, J. M.*; Kek
linen, P.*; Pulkkanen, V.-M.*; Moreno, L.*; Iraola, A.*; Trinchero, P.*; Hokr, M.*; 
ha, J.*; Havlov
, V.*; Trpko
ov, D.*; et al.
Nuclear Technology, 209(11), p.1765 - 1784, 2023/11
Times Cited Count：2 Percentile：87.3(Nuclear Science & Technology)Osaka, Masahiko; Miwa, Shuhei; Nakajima, Kunihisa; Di Lemma, F. G.*; Suzuki, Chikashi; Miyahara, Naoya; Kobata, Masaaki; Okane, Tetsuo; Suzuki, Eriko
JAEA-Review 2016-026, 32 Pages, 2016/12
JAEA-Review-2016-026.pdf:6.18MB
A fundamental research program on fission product (FP) chemistry has started since 2012 for the purpose of establishment of a FP chemistry database in each region of LWR under severe accident and improvement of FP chemical models based on the database. Research outputs are reflected as fundamental knowledge to both the research and development of decommissioning of Fukushima Daiichi Nuclear Power Station (1F) and enhancement of LWR safety. Four research items have thus been established considering the specific issues of 1F and the priority in the source term research area, as follows: effects of boron (B) release kinetics and thermal-hydraulic conditions on FP behavior, cesium (Cs) chemisorption and reactions with structural materials, enlargement of a thermodynamic and thermophysical properties database for FP compounds and development of experimental and analytical techniques for the reproduction of FP behavior and for direct measurement methods of chemical form of FP compounds. In this report, the research results and progress for the year 2015 are described. The main accomplishment was the installation of a reproductive test facility for FP release and transport behavior. Moreover, basic knowledge about the Cs chemisorption behavior was also obtained. In addition to the four research items, a further research item is being considered for deeper interpretation of FP behavior by the analysis of samples outside of the 1F units.
Oba, Toshihiro; Suetsugu, Hidehiko*; Yano, Masaya*; Kato, Chiaki; Yanagihara, Takao
JAERI-Tech 2002-082, 47 Pages, 2003/01
JAERI-Tech-2002-082.pdf:1.87MB
The demonstration test for evaluating reliability of the acid recovery evaporator at Rokkasho Reprocessing Plant has been carried out at JAERI. For the nondestructive measurement of the thickness of heat transfer tubes of the acid recovery evaporator in corrosion test, we have developed thickness measurement apparatus for heat transfer tubes by ultrasonic immersion method with high resolution. The ultrasonic prove in a heat transfer tube can be moved vertically and radially. The results obtained by this apparatus coincident well with those obtained by a destructive method using an optical microscope.
Yonomoto, Taisuke; Anoda, Yoshinari
IAEA-TECDOC-1149, p.233 - 246, 2000/05
no abstracts in English
Noguchi, Hiroshi
Nihon Genshiryoku Gakkai-Shi, 39(11), p.915 - 916, 1997/00
no abstracts in English
Ikawa, Koji; Ihara, Hitoshi; Nishimura, Hideo
JAERI-M 93-182, 160 Pages, 1993/09
no abstracts in English
Suzuki, Motoe; Nishio, Gunji; Takada, Junichi; Tsukamoto, Michio; Koike, Tadao
JAERI 1328, 90 Pages, 1993/01
no abstracts in English
Sawa, Kazuhiro; ; *; Endo, Yasuichi; Shiozawa, Shusaku;
JAERI-M 91-207, 34 Pages, 1991/12
no abstracts in English
Kukita, Yutaka; *; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; et al.
JAERI-M 90-039, 122 Pages, 1990/03
no abstracts in English
Kukita, Yutaka; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; Yonomoto, Taisuke; et al.
JAERI-M 89-225, 117 Pages, 1990/01
no abstracts in English
; ; ; *; *; *
Nuclear Safeguards Technology 1986,Vol.1, p.341 - 352, 1987/00
no abstracts in English
; Kondo, Tatsuo
Boshoku Gijutsu, 32(9), p.503 - 511, 1983/00
no abstracts in English
; ; ; *; *
Nuclear Safeguards Technology,Vol.1, p.499 - 512, 1983/00
no abstracts in English
;
Nucl.Eng.Des., 74(2), p.165 - 171, 1982/00
Times Cited Count：4 Percentile：50.97(Nuclear Science & Technology)no abstracts in English
Ibe, Junya*; Aso, Megumi*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*
no journal, ,
Since waste salt generated from pyro-reprocessing test which contains uranium can easily capture moisture and corrode equipment, further treatment technology for decontamination. Oxides are added as oxygen donor in the melts, and then uranium is separated from the salt as precipitates. In the next step, melt bath components are evaporated by a vacuum distillation. First, LiCl-KCl eutectic and NaCl-2CsCl salts were used as melt baths, lithium oxide was used as a precipitant, and cerium chloride was used as uranium surrogate for testing the precipitation process. Next, a distillation line has been constructed and the best condition for distillation has been searched. Amount of the precipitates increased with increasing the amount of oxide, and recovery ratio of cerium must potentially depend on solubility of oxychloride into the bath salts. It is considered that oxychloride was formed by the similarity in EXAFS oscillation and X-ray diffraction patterns.
