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Evaluation of tungsten temperature of divertor during Ex-LOCA and evaluation of corrosion depth of graphite during LOVA in fusion experimental reactor

Technical Report:

Abstract

This paper deals with the evaluation of tungsten temperature of divertor during external loss of coolant accident (Ex-LOCA) in connection with the safety design of nuclear fusion experimental reactor. The present result and the results of U.S.A. and EC are discussed in the conceptual design of International Thermonuclear Engineering Reactor (ITER), and reference LOCA temperature is recommended to be 700{+-}100degC for divertor, lasting 7 days. Corrosion depth of graphite tile of the first wall is evaluated during loss of vacuum accident (LOVA). The corrosion depth, duration time for the corrosion, generating heat, and volume of carbon monoxide are calculated when the carbon is attacked by oxygen in the air contained in the volume of the vacuum vessel. It is found that the results are not significant if fresh air does not continue to enter the vacuum vessel. (author).
Authors:
Ogawa, Masuro; [1]  Takatsu, Hideyuki; Iida, Hiromasa; Seki, Yasushi
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Aug 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-119
Reference Number:
SCA: 700450; PA: JPN-91:011144; SN: 92000630560
Resource Relation:
Other Information: PBD: Aug 1991
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER TOKAMAK; ACCIDENTS; DIVERTORS; FIRST WALL; TUNGSTEN; TEMPERATURE DISTRIBUTION; VACUUM SYSTEMS; THERMONUCLEAR REACTOR COOLING SYSTEMS; CORROSION; 700450; BLANKETS AND COOLING SYSTEMS
OSTI ID:
10109000
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE92750953; TRN: JP9111144
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
33 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Ogawa, Masuro, Takatsu, Hideyuki, Iida, Hiromasa, and Seki, Yasushi. Evaluation of tungsten temperature of divertor during Ex-LOCA and evaluation of corrosion depth of graphite during LOVA in fusion experimental reactor. Japan: N. p., 1991. Web.
Ogawa, Masuro, Takatsu, Hideyuki, Iida, Hiromasa, & Seki, Yasushi. Evaluation of tungsten temperature of divertor during Ex-LOCA and evaluation of corrosion depth of graphite during LOVA in fusion experimental reactor. Japan.
Ogawa, Masuro, Takatsu, Hideyuki, Iida, Hiromasa, and Seki, Yasushi. 1991. "Evaluation of tungsten temperature of divertor during Ex-LOCA and evaluation of corrosion depth of graphite during LOVA in fusion experimental reactor." Japan.
@misc{etde_10109000,
title = {Evaluation of tungsten temperature of divertor during Ex-LOCA and evaluation of corrosion depth of graphite during LOVA in fusion experimental reactor}
author = {Ogawa, Masuro, Takatsu, Hideyuki, Iida, Hiromasa, and Seki, Yasushi}
abstractNote = {This paper deals with the evaluation of tungsten temperature of divertor during external loss of coolant accident (Ex-LOCA) in connection with the safety design of nuclear fusion experimental reactor. The present result and the results of U.S.A. and EC are discussed in the conceptual design of International Thermonuclear Engineering Reactor (ITER), and reference LOCA temperature is recommended to be 700{+-}100degC for divertor, lasting 7 days. Corrosion depth of graphite tile of the first wall is evaluated during loss of vacuum accident (LOVA). The corrosion depth, duration time for the corrosion, generating heat, and volume of carbon monoxide are calculated when the carbon is attacked by oxygen in the air contained in the volume of the vacuum vessel. It is found that the results are not significant if fresh air does not continue to enter the vacuum vessel. (author).}
place = {Japan}
year = {1991}
month = {Aug}
}