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Title: Displacement damage in the first structural wall of an inertial confinement fusion reactor: dependence on blanket design

Abstract

In this study we investigate how the design of the neutron blanket effects the displacement damage rate in the first structural wall (FSW) of an Inertial Confinement Fusion (ICF) reactor. Two generic configurations are examined; in the first, the steel wall is directly exposed to the fusion neutrons, whereas in the second, the steel wall is protected by inner blanket of lithium with an effective thickness of 1-m. The latter represents a HYLIFE-type design, which has been shown to have displacement damage rates an order of magnitude lower than unprotected wall designs. The two basic configurations were varied to show how the dpa rate changes as the result of (1) adding a Li blanket outside the FSW, (2) adding a neutron reflector (graphite) outside the FSW, and (3) changing the position of the inner lithium blanket relative to the FSW. The effects of neutron moderation in the compressed DT-target are also shown, and the unprotected and protected configurations compared.

Authors:
Publication Date:
Research Org.:
Lawrence Livermore National Lab., CA (USA)
OSTI Identifier:
6712629
Alternate Identifier(s):
OSTI ID: 6712629; Legacy ID: DE84015082
Report Number(s):
UCID-20121
ON: DE84015082
DOE Contract Number:
W-7405-ENG-48
Resource Type:
Technical Report
Resource Relation:
Other Information: Portions are illegible in microfiche products. Original copy available until stock is exhausted
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BREEDING BLANKETS; DESIGN; FIRST WALL; HYLIFE CONVERTER; DISPLACEMENT RATES; GRAPHITE; LITHIUM; PHYSICAL RADIATION EFFECTS; SHIELDING; ALKALI METALS; CARBON; ELEMENTAL MINERALS; ELEMENTS; LASER FUSION REACTORS; METALS; MINERALS; NONMETALS; RADIATION EFFECTS; REACTOR COMPONENTS; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS 700201* -- Fusion Power Plant Technology-- Blanket Engineering

Citation Formats

Meier, W.R. Displacement damage in the first structural wall of an inertial confinement fusion reactor: dependence on blanket design. United States: N. p., 1984. Web. doi:10.2172/6712629.
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Meier, W.R. Displacement damage in the first structural wall of an inertial confinement fusion reactor: dependence on blanket design. United States. doi:10.2172/6712629.
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Meier, W.R. Fri . "Displacement damage in the first structural wall of an inertial confinement fusion reactor: dependence on blanket design". United States. doi:10.2172/6712629. https://www.osti.gov/servlets/purl/6712629.
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@article{osti_6712629,
title = {Displacement damage in the first structural wall of an inertial confinement fusion reactor: dependence on blanket design},
author = {Meier, W.R.},
abstractNote = {In this study we investigate how the design of the neutron blanket effects the displacement damage rate in the first structural wall (FSW) of an Inertial Confinement Fusion (ICF) reactor. Two generic configurations are examined; in the first, the steel wall is directly exposed to the fusion neutrons, whereas in the second, the steel wall is protected by inner blanket of lithium with an effective thickness of 1-m. The latter represents a HYLIFE-type design, which has been shown to have displacement damage rates an order of magnitude lower than unprotected wall designs. The two basic configurations were varied to show how the dpa rate changes as the result of (1) adding a Li blanket outside the FSW, (2) adding a neutron reflector (graphite) outside the FSW, and (3) changing the position of the inner lithium blanket relative to the FSW. The effects of neutron moderation in the compressed DT-target are also shown, and the unprotected and protected configurations compared.},
doi = {10.2172/6712629},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jul 13 00:00:00 EDT 1984},
month = {Fri Jul 13 00:00:00 EDT 1984}
}
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Technical Report:
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DOI:  10.2172/6712629
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