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Titolo:
Tritium contamination and decontamination study on materials for ITER remote handling equipment
Autore:
Oya, Y; Kobayashi, K; Shu, W; Higashijima, T; Hayashi, T; Ohira, S; Obara, K; Nishi, M; Shibanuma, K; Koizumi, K;
Indirizzi:
Japan Atom Energy Res Inst, Dept Fus Engn Res, Tritium Eng Lab, Tokai, Ibaraki 3191195, Japan Japan Atom Energy Res Inst Tokai Ibaraki Japan 3191195aki 3191195, Japan Japan Atom Energy Res Inst, Dept Fus Engn Res, Reactor Struct Lab, Tokai, Ibaraki 3191195, Japan Japan Atom Energy Res Inst Tokai Ibaraki Japan 3191195 aki 3191195, Japan
Titolo Testata:
FUSION ENGINEERING AND DESIGN
fascicolo: 4, volume: 55, anno: 2001,
pagine: 449 - 455
SICI:
0920-3796(200109)55:4<449:TCADSO>2.0.ZU;2-P
Fonte:
ISI
Lingua:
ENG
Soggetto:
TRITIATED-WATER;
Keywords:
tritium; contamination; decontamination; ITER; remote handling;
Tipo documento:
Article
Natura:
Periodico
Settore Disciplinare:
Engineering, Computing & Technology
Citazioni:
13
Recensione:
Indirizzi per estratti:
Indirizzo: Oya, Y Univ Tokyo, Radioisotope Ctr, Bunkyo Ku, 2-11-16 Yayoi, Tokyo 1130032, Japan Univ Tokyo 2-11-16 Yayoi Tokyo Japan 1130032 Tokyo 1130032, Japan
Citazione:
Y. Oya et al., "Tritium contamination and decontamination study on materials for ITER remote handling equipment", FUSION ENG, 55(4), 2001, pp. 449-455

Abstract

Several materials, lenses, dry bearings and cables were exposed to a tritiated moisture environment to study the behavior of tritium contamination oncandidate materials for ITER remote handling equipment. To optimize the tritium removal procedure, decontamination experiments using a gas purge withthree different moisture concentrations were also performed. The surface tritium concentrations of CeO2 containing alkaline barium glass (NB), CeO2 containing lead glass (LX) and synthetic quartz (Quartz) after the exposure experiments were 7.80, 10.94 and 0.67 Bq/cm(2), respectively. It was found that the tritium concentration was influenced by the compositions of the materials. The concentrations of tritium on type 831 (solid lubrication material: graphite) and type 237 (solid lubrication material: tungsten disulfate) dry bearings after the exposure experiments were 89.80 and 31.78 Bq/cm(2), respectively. The tritium concentration in an electric cable tested was 5014 Bq/g after HTO moisture exposure. The tritium concentrations of lenses,LX, as typical experimental results, decreased to 2.72, 4.42 and 3.89 Bq/cm(2) by purging with the moist air, dry air and dry N-2, respectively. The tritium concentrations of dry bearing, type 831 dropped to 6.61, 9.42 and 10.16 Bq/cm(2) by the same three decontamination treatments, respectively. Alarge decontamination factor of 13.6 was achieved in the case of type 831 dry bearing with a moist air purge. The tritium concentration in the electric cable was 3236 Bq/g after a moist air purge, and the decontamination factor was as low as 1.6. Therefore, decontamination with a moist air purge isnot so effective for the electric cable. (C) 2001 0Elsevier Science B.V. All rights reserved.

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Documento generato il 06/04/20 alle ore 01:57:15