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Material and design considerations for the carbon armored ITER divertor

Abstract

The properties of materials for the carbon armored ITER divertor were evaluated from literature and manufacturers` documentation. Most of these data, however, have been not known or not published yet. We have evaluated an optimum data set of the candidate materials of the ITER divertor, which were needed for finite element analyses (FEM). The materials evaluated are as follows; MFC-1, CX2002U, SEP-N112, P-130, IG-430U for the carbon based materials, and Oxygen Free Copper (OFCu), Dispersion Strengthened Copper (DSCu), TZM, W5Re and W-Cu as a heat sink material. It should be noted that W-Cu is first proposed for a heat sink application of the ITER divertor plate. The finite element analyses were performed for the residual stress induced by brazing, thermal response and thermal stresses under a uniform heat flux of 15 MW/m{sup 2} to the plasma facing surface. The stress free temperature of 750degC is assumed for the residual stress by brazing. Ten different geometries of the divertor were considered in the analyses including possible material combinations. The FEM results show that the material combinations of MFC-1 and W-30Cu or DSUc in the flat-plate geometry satisfy the presently accepted ITER requirements. The combinations of CX2002U and TZM or W5Re is  More>>
Authors:
Smid, I; Akiba, Masato; Araki, Masanori; Suzuki, Satoshi; Satoh, Kazuyoshi [1] 
  1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Publication Date:
Jul 01, 1993
Product Type:
Technical Report
Report Number:
JAERI-M-93-149
Reference Number:
SCA: 700420; PA: JPN-93:012076; EDB-94:027919; ERA-19:011279; NTS-94:017575; SN: 94001140285
Resource Relation:
Other Information: PBD: Jul 1993
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER TOKAMAK; DIVERTORS; GRAPHITE; SPECIFICATIONS; FINITE ELEMENT METHOD; THERMAL STRESSES; THERMAL SHOCK; THERMODYNAMIC PROPERTIES; COPPER COMPOUNDS; CRITICAL HEAT FLUX; HEAT TRANSFER; NUMERICAL SOLUTION; 700420; PLASMA-FACING COMPONENTS
OSTI ID:
10120822
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE94737854; TRN: JP9312076
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
208 p.
Announcement Date:
Jun 30, 2005

Citation Formats

Smid, I, Akiba, Masato, Araki, Masanori, Suzuki, Satoshi, and Satoh, Kazuyoshi. Material and design considerations for the carbon armored ITER divertor. Japan: N. p., 1993. Web.
Smid, I, Akiba, Masato, Araki, Masanori, Suzuki, Satoshi, & Satoh, Kazuyoshi. Material and design considerations for the carbon armored ITER divertor. Japan.
Smid, I, Akiba, Masato, Araki, Masanori, Suzuki, Satoshi, and Satoh, Kazuyoshi. 1993. "Material and design considerations for the carbon armored ITER divertor." Japan.
@misc{etde_10120822,
title = {Material and design considerations for the carbon armored ITER divertor}
author = {Smid, I, Akiba, Masato, Araki, Masanori, Suzuki, Satoshi, and Satoh, Kazuyoshi}
abstractNote = {The properties of materials for the carbon armored ITER divertor were evaluated from literature and manufacturers` documentation. Most of these data, however, have been not known or not published yet. We have evaluated an optimum data set of the candidate materials of the ITER divertor, which were needed for finite element analyses (FEM). The materials evaluated are as follows; MFC-1, CX2002U, SEP-N112, P-130, IG-430U for the carbon based materials, and Oxygen Free Copper (OFCu), Dispersion Strengthened Copper (DSCu), TZM, W5Re and W-Cu as a heat sink material. It should be noted that W-Cu is first proposed for a heat sink application of the ITER divertor plate. The finite element analyses were performed for the residual stress induced by brazing, thermal response and thermal stresses under a uniform heat flux of 15 MW/m{sup 2} to the plasma facing surface. The stress free temperature of 750degC is assumed for the residual stress by brazing. Ten different geometries of the divertor were considered in the analyses including possible material combinations. The FEM results show that the material combinations of MFC-1 and W-30Cu or DSUc in the flat-plate geometry satisfy the presently accepted ITER requirements. The combinations of CX2002U and TZM or W5Re is considered a good choice in terms of residual and thermal stresses, whereas the surface temperature exceeds the ITER requirements. (author) 106 refs.}
place = {Japan}
year = {1993}
month = {Jul}
}