Published 2008 | Version v1
Report

Divertor design study on compact DEMO reactor for handling of huge exhaust power

Creators

  • 1. Japan Atomic Energy Agency, Naka (Japan)

Description

Conceptual designing of the divertor system is required for DEMO reactor next to ITER for the handling of huge exhaust power. For the divertor design study using SOLDOR/NEUT2D code in the compact DEMO reactor, Slim CS, we find out a prospective divertor design to hold the detached divertor condition within allowable heat load for the first time. Although the heating power on Slim CS increases ∼ 6 times larger than that for ITER, the tolerable heat load on divertor target is restricted to 10 MW/m2, which is less by half than that for ITER. Assuming the heating power of 500 MW and ion out flux of ∼ 1 x 1023 s-1 with a low-aspect ratio plasmas and vertical divertor target, the peak heat load is estimated to be 50 MW/m2 on the outer target with attached condition. This value exceeds significantly the allowable limit of 10 MW/m2. By installing the V-shaped corner in bottom of the outer divertor target and introducing argon impurity, the detached condition with higher particle recycling and radiation loss conditions is obtained, and the peak heat load is successfully reduced to 7.2 MW/m2. (author)

Part of:
22. IAEA fusion energy conference: 'Celebrating fifty years of fusion... entering into the burning plasma era'. Book of abstracts

Additional details

Publishing Information

Imprint Title
22. IAEA fusion energy conference: 'Celebrating fifty years of fusion... entering into the burning plasma era'. Book of abstracts
Imprint Pagination
295 p.
Journal Page Range
p. 122
Report number
INIS-XA--08N0893

Conference

Title
22. IAEA fusion energy conference - 50th Anniversary Controlled Nuclear Fusion Research
Acronym
FEC 2008
Dates
13-18 Oct 2008
Place
Geneva (Switzerland)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
40004347
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ARGON; ASPECT RATIO; DESIGN; DIVERTORS; HEATING; HEATING LOAD; ITER TOKAMAK; LOSSES; PARTICLES; PEAKS; PLASMA; PLASMA IMPURITIES; RECYCLING
Descriptors DEC
CLOSED PLASMA DEVICES; DIMENSIONLESS NUMBERS; ELEMENTS; FLUIDS; GASES; IMPURITIES; NONMETALS; RARE GASES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Secondary number(s)
FT/P3--10