You need JavaScript to view this

ITER plasma facing components

Miscellaneous:

Abstract

This document summarizes results of the Conceptual Design Activities (1988-1990) for the International Thermonuclear Experimental Reactor (ITER) project, namely those that pertain to the plasma facing components of the reactor vessel, of which the main components are the first wall and the divertor plates. After an introduction and an executive summary, the principal functions of the plasma-facing components are delineated, i.e., (i) define the low-impurity region within which the plasma is produced, (ii) absorb the electromagnetic radiation and charged-particle flux from the plasma, and (iii) protect the blanket/shield components from the plasma. A list of critical design issues for the divertor plates and the first wall is given, followed by discussions of the divertor plate design (including the issues of material selection, erosion lifetime, design concepts, thermal and mechanical analysis, operating limits and overall lifetime, tritium inventory, baking and conditioning, safety analysis, manufacture and testing, and advanced divertor concepts) and the first wall design (armor material and design, erosion lifetime, overall design concepts, thermal and mechanical analysis, lifetime and operating limits, tritium inventory, baking and conditioning, safety analysis, manufacture and testing, an alternative first wall design, and the limiters used instead of the divertor plates during start-up). Refs, figs and  More>>
Authors:
Kuroda, T; Vieider, G; Akiba, M [1] 
  1. and others
Publication Date:
Oct 01, 1991
Product Type:
Miscellaneous
Report Number:
INIS-mf-13062
Reference Number:
SCA: 700480; PA: AIX-23:015808; SN: 92000647317
Resource Relation:
Journal Issue: No. 30; Other Information: PBD: Oct 1991; Related Information: ITER documentation series
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; DIVERTORS; EXPERIMENT PLANNING; SPECIFICATIONS; WALL LOADING; FIRST WALL; ITER TOKAMAK; LIMITERS; START-UP; ACTIVATION ENERGY; BAKING; EROSION; HYDRAULICS; LOSS OF COOLANT; NEUTRON FLUX; REACTOR SAFETY; RESEARCH PROGRAMS; RUNAWAY ELECTRONS; THERMAL FATIGUE; THERMONUCLEAR REACTOR COOLING SYSTEMS; TRITIUM; 700480; COMPONENT DEVELOPMENT; MATERIALS STUDIES
OSTI ID:
10113099
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ON: DE92615478; TRN: XA9130325015808
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
148 p.
Announcement Date:
Jun 30, 2005

Miscellaneous:

Citation Formats

Kuroda, T, Vieider, G, and Akiba, M. ITER plasma facing components. IAEA: N. p., 1991. Web.
Kuroda, T, Vieider, G, & Akiba, M. ITER plasma facing components. IAEA.
Kuroda, T, Vieider, G, and Akiba, M. 1991. "ITER plasma facing components." IAEA.
@misc{etde_10113099,
title = {ITER plasma facing components}
author = {Kuroda, T, Vieider, G, and Akiba, M}
abstractNote = {This document summarizes results of the Conceptual Design Activities (1988-1990) for the International Thermonuclear Experimental Reactor (ITER) project, namely those that pertain to the plasma facing components of the reactor vessel, of which the main components are the first wall and the divertor plates. After an introduction and an executive summary, the principal functions of the plasma-facing components are delineated, i.e., (i) define the low-impurity region within which the plasma is produced, (ii) absorb the electromagnetic radiation and charged-particle flux from the plasma, and (iii) protect the blanket/shield components from the plasma. A list of critical design issues for the divertor plates and the first wall is given, followed by discussions of the divertor plate design (including the issues of material selection, erosion lifetime, design concepts, thermal and mechanical analysis, operating limits and overall lifetime, tritium inventory, baking and conditioning, safety analysis, manufacture and testing, and advanced divertor concepts) and the first wall design (armor material and design, erosion lifetime, overall design concepts, thermal and mechanical analysis, lifetime and operating limits, tritium inventory, baking and conditioning, safety analysis, manufacture and testing, an alternative first wall design, and the limiters used instead of the divertor plates during start-up). Refs, figs and tabs.}
issue = {No. 30}
place = {IAEA}
year = {1991}
month = {Oct}
}