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Sn in concrete rubbleDo, V. K.; Furuse, Takahiro; Ota, Yuki; Iwahashi, Hiroyuki; Hirosawa, Takashi; Watanabe, Masahisa; Sato, Soichi
Journal of Radioanalytical and Nuclear Chemistry, 331(12), p.5631 - 5640, 2022/12
Times Cited Count：2 Percentile：50.96(Chemistry, Analytical)Sn is one of the long-lived fission products that might have been released into the environment after the Fukushima nuclear accident in Japan in 2011. The presence of radionuclides must be monitored for the proper treatment of wastes obtained from decommissioning accident-related nuclear facilities and the surrounding environment. In the work, we propose a reliable method for verifying the presence of Sn in construction materials by combining the HCl-free solid phase extraction on TEVA resin and a selective measurement by inductively coupled plasma tandem mass spectrometry (ICP-MS/MS). The method has been optimized and characterized step by step. More than 95% of chemical recovery was achieved for Sn from typical concrete matrixes. The interference caused by an isobar Te and possible polyatomic interferences from matrixes were effectively suppressed by the developed chemical separation and the tandem MS/MS configuration. The total decontamination factor for the Te interference was of the order of 10
. The estimated method detection limit for Sn in concrete as measured at m/z = 160 was 12.1 pg g
, which is equivalent to 6.1 mBq g.
Okita, Shoichiro; Nagaya, Yasunobu; Fukaya, Yuji
Journal of Nuclear Science and Technology, 58(9), p.992 - 998, 2021/09
Times Cited Count：2 Percentile：30.55(Nuclear Science & Technology)Kobayashi, Yasuhiko; Funayama, Tomoo; Wada, Seiichi; Hamada, Nobuyuki*
JAERI-Conf 2005-012, 53 Pages, 2005/09
JAERI-Conf-2005-012.pdf:5.11MB
no abstracts in English
Enoeda, Mikio
JAERI-Conf 2004-012, 237 Pages, 2004/07
JAERI-Conf-2004-012.pdf:44.1MB
This report is the Proceedings of "the Eleventh International Workshop on Ceramic Breeder Blanket Interactions" which was held as a workshop on ceramic breeders Under the IEA Implementing Agreement on the Nuclear Technology of Fusion Reactors, and the Japan-US Fusion Collaboration Framework. In the workshop, information exchange was performed for designs of solid breeder blankets and test blankets in EU, Russia and Japan, recent results of irradiation tests, HICU, EXOTIC-8 and the irradiation tests by IVV-2M, modeling study on tritium release behavior of Li
TiO
and other breeders, fabrication technology developments and characterization of the LiTiO and Li
SiO pebbles, research on measurements and modeling of thermo-mechanical behaviors of LiTiO and LiSiO pebbles, and interfacing issues, such as, fabrication technology for blanket box structure, neutronics experiments of blanket mockups by fusion neutron source and tritium recovery system.
Kikuchi, Kenji; Saito, Shigeru; Kurata, Yuji; Futakawa, Masatoshi; Sasa, Toshinobu; Oigawa, Hiroyuki; Wakai, Eiichi; Umeno, Makoto*; Mizubayashi, Hiroshi*; Miura, Kuniaki*
JSME International Journal, Series B, 47(2), p.332 - 339, 2004/05
Lead bismuth eutectic (LBE) is favored by spallation neutron sources and coolant in the sub-critical reactor at the accelerator driven nuclear transmutation system (ADS). Technical issues of ADS are material technology of how to compromise with flowing lead bismuth, high-energy proton accelerator technology and a sub-critical reactor system technology. This paper describes LBE technology developed at JAERI. First a scenario in order to realize the ADS is shown. The concept of spallation target test facility is introduced with a target design of thermo-fluid dynamics. Base data of flow rate and temperature of Pb-Bi during LBE circulation are described. The results of LBE loop operation under the flowing conditions of target design concept are reported. The stagnant corrosion tests were done to know the controlling parameters among the various steels. The tube-type oxygen sensor with having the solid electrolyte was studied. Cleaning techniques were developed to remove LBE from materials.
Kurata, Yuji; Kikuchi, Kenji; Saito, Shigeru; Kamata, Kinya*; Kitano, Teruaki*; Oigawa, Hiroyuki
Proceedings of 4th International Workshop on the Utilisation and Reliability of High Power Proton Accelerators, p.267 - 277, 2004/05
R&D on lead-bismuth technology have been conducted for accelerator driven system. From the test results of 316SS using JLBL-1 for 3000h without active oxygen control, mass transfer from high temperature to low temperature parts was observed. It was found that deposition of Pb/Bi and Fe-Cr grains in the annular channel of the electro-magnetic pump caused plugging and decrease in flow rate. The modification of the loop system brought about a good effect on operation. Significant erosion/corrosion was not observed in the experiment using MES loop for 1000h under 10
wt.% oxygen condition. The results of static corrosion tests showed the following: corrosion depth decreased at 450
C with increasing Cr content in steels while corrosion depth of JPCA and 316SS became larger due to ferritization caused by dissolution of Ni and Cr at 550C. Si-added steel exhibited good corrosion resistance at 550C.
Kosaku, Yasuo; Kuroda, Toshimasa*; Enoeda, Mikio; Hatano, Toshihisa; Sato, Satoshi; Sato, Shinichi*; Osaki, Toshio*; Miki, Nobuharu*; Akiba, Masato
JAERI-Tech 2003-058, 69 Pages, 2003/06
JAERI-Tech-2003-058.pdf:5.86MB
The design of the breeding blanket in ITER applies pebble bed breeder in tube (BIT) surrounded by multiplier pebble bed. It is assumed to use the same module support mechanism and coolant manifolds and coolant system as the shielding blankets. This work focuses on the verification of the design of the breeding blanket, from the viewpoints which is especially unique to the pebble bed type breeding blanket, such as, tritium breeding performance, tritium inventory and release behavior and thermo-mechanical performance of the ITER breeding blanket.
Miyamoto, Yukihiro; Ikeno, Koichi; Akiyama, Shigenori*; Harada, Yasunori
JAERI-Tech 2002-086, 43 Pages, 2002/11
Description is given for the characteristic radiation environment for the High Intensity Proton Accelerator Facility and the design concept of the radiation control system of it. The facility is a large scale accelerator complex consisting of high energy proton accelerators carrying the highest beam intensity in the world and the related experimental facilities and therefore provides various issues relevant to the radiation environment. The present report describes the specifications for the radiation control system for the facility, determined in consideration of these characteristics.
Yanagi, Yoshihiko*; Kosaku, Yasuo; Hatano, Toshihisa; Kuroda, Toshimasa*; Enoeda, Mikio; Akiba, Masato
JAERI-Tech 2002-046, 45 Pages, 2002/05
JAERI-Tech-2002-046.pdf:2.61MB
no abstracts in English
Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.
JAERI-Tech 2001-078, 120 Pages, 2001/12
This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.
Hamamatsu, Kiyotaka; Fukuyama, Atsushi*
Fusion Engineering and Design, 53(1-4), p.53 - 58, 2001/01
Times Cited Count：33 Percentile：89.46(Nuclear Science & Technology)no abstracts in English
Hamamatsu, Kiyotaka; Fukuyama, Atsushi*
Plasma Physics and Controlled Fusion, 42(12), p.1309 - 1320, 2000/12
Times Cited Count：19 Percentile：51.23(Physics, Fluids & Plasmas)no abstracts in English
Hamamatsu, Kiyotaka; Fukuyama, Atsushi*
JAERI-Research 2000-053, 13 Pages, 2000/11
JAERI-Research-2000-053.pdf:1.78MB
no abstracts in English
Nagame, Yuichiro; Zhao, Y.*; Nishinaka, Ichiro; Otsuki, Tsutomu*; Tanikawa, Masashi*; Tsukada, Kazuaki; Sueki, Keisuke*; Ichikawa, Shinichi; Nakahara, Hiromichi*
1st International Conference on the Chemistry and Physics of the Transactinide Elements; Extended Abstracts, 4 Pages, 1999/00
no abstracts in English
U
O
Fujino, Takeo*; Sato, Nobuaki*; Yamada, Kota*; *; Fukuda, Kosaku; Serizawa, Hiroyuki; Shiratori, Tetsuo
Journal of Nuclear Materials, 265(1-2), p.154 - 160, 1999/00
Times Cited Count：6 Percentile：45.48(Materials Science, Multidisciplinary)no abstracts in English
Miyamoto, Yukihiro; ; Harada, Yasunori
JAERI-Tech 98-039, 44 Pages, 1998/09
no abstracts in English
Yamashita, Toshiyuki; ; Tsuji, Toshihide*; *
Journal of Alloys and Compounds, 271-273, p.404 - 407, 1998/00
Times Cited Count：9 Percentile：55.04(Chemistry, Physical)no abstracts in English
Sato, Satoshi; Furuya, Kazuyuki; Kuroda, Toshimasa*; Kurasawa, Toshimasa; *; Hatano, Toshihisa; Takatsu, Hideyuki; Osaki, Toshio*
16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 1, p.202 - 205, 1996/00
no abstracts in English
Adachi, Takeo; Nakahara, Yoshinori; Kono, Nobuaki; Gunji, Katsubumi; ; ; ; Kato, Kaneharu; Tachikawa, Enzo; *; et al.
Journal of Nuclear Science and Technology, 31(10), p.1119 - 1129, 1994/10
Times Cited Count：8 Percentile：60.14(Nuclear Science & Technology)no abstracts in English
*; Asano, Yoshihiro; *; Sudo, Norimichi*
SSR-93-002, 0, 67 Pages, 1993/12
no abstracts in English
