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

Technical Report · Fri Jul 13 04:00:00 EDT 1984

DOI:https://doi.org/10.2172/6712629· OSTI ID:6712629

Meier, W R

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.

• Research Organization: Lawrence Livermore National Lab., CA (USA)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6712629
• Report Number(s): UCID-20121; ON: DE84015082
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ALKALI METALS
BREEDING BLANKETS
CARBON
DESIGN
DISPLACEMENT RATES
ELEMENTAL MINERALS
ELEMENTS
FIRST WALL
GRAPHITE
HYLIFE CONVERTER
LASER FUSION REACTORS
LITHIUM
METALS
MINERALS
NONMETALS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
SHIELDING
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS