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Development of integrated insulation joint for cooling pipe in tokamak reactor

Technical Report:

Abstract

In a tokamak fusion reactor, an electrically insulated part is needed for an in-vessel piping system in order to break an electric circuit loop. When a closed loop is formed in the piping system, large induced electromagnetic forces during a plasma disruption (rapid plasma current quench) could give damages on the piping system. Ceramic brazing joint is a conventional method for the electric circuit break, but an application to the fusion reactor is not feasible due to its brittleness. Here, a stainless steel/ceramics/stainless steel functionally gradient material (FGM) has been proposed and developed as an integrated insulation joint of the piping system. Both sides of the joint can be welded to the main pipes, and expected to be reliable even in the fusion reactor environment. When the FGM joint is manufactured by way of a sintering process, a residual thermal stress is the key issue. Through detailed computations of the residual thermal stress and several trial productions, tubular elements of FGM joints have been successfully manufactured. (author).
Authors:
Nishio, Satoshi; Abe, Tetsuya; [1]  Kawamura, Masashi; Yamazaki, Seiichiro
  1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Publication Date:
Aug 01, 1994
Product Type:
Technical Report
Report Number:
JAERI-Tech-94-006
Reference Number:
SCA: 700480; PA: JPN-94:012128; EDB-95:026589; SN: 95001319936
Resource Relation:
Other Information: PBD: Aug 1994
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; PIPE JOINTS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; COOLING; PIPES; PIPE FITTINGS; COMPOSITE MATERIALS; THERMAL STRESSES; 700480; COMPONENT DEVELOPMENT; MATERIALS STUDIES
OSTI ID:
10109257
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE95737220; TRN: JP9412128
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
23 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Nishio, Satoshi, Abe, Tetsuya, Kawamura, Masashi, and Yamazaki, Seiichiro. Development of integrated insulation joint for cooling pipe in tokamak reactor. Japan: N. p., 1994. Web.
Nishio, Satoshi, Abe, Tetsuya, Kawamura, Masashi, & Yamazaki, Seiichiro. Development of integrated insulation joint for cooling pipe in tokamak reactor. Japan.
Nishio, Satoshi, Abe, Tetsuya, Kawamura, Masashi, and Yamazaki, Seiichiro. 1994. "Development of integrated insulation joint for cooling pipe in tokamak reactor." Japan.
@misc{etde_10109257,
title = {Development of integrated insulation joint for cooling pipe in tokamak reactor}
author = {Nishio, Satoshi, Abe, Tetsuya, Kawamura, Masashi, and Yamazaki, Seiichiro}
abstractNote = {In a tokamak fusion reactor, an electrically insulated part is needed for an in-vessel piping system in order to break an electric circuit loop. When a closed loop is formed in the piping system, large induced electromagnetic forces during a plasma disruption (rapid plasma current quench) could give damages on the piping system. Ceramic brazing joint is a conventional method for the electric circuit break, but an application to the fusion reactor is not feasible due to its brittleness. Here, a stainless steel/ceramics/stainless steel functionally gradient material (FGM) has been proposed and developed as an integrated insulation joint of the piping system. Both sides of the joint can be welded to the main pipes, and expected to be reliable even in the fusion reactor environment. When the FGM joint is manufactured by way of a sintering process, a residual thermal stress is the key issue. Through detailed computations of the residual thermal stress and several trial productions, tubular elements of FGM joints have been successfully manufactured. (author).}
place = {Japan}
year = {1994}
month = {Aug}
}