Published 1993
| Version v1
Journal article
Neutron damage and activation of the first wall of inertial confinement fusion reactors: recycling and waste disposal
Creators
- 1. Universidad Politecnica de Madrid (Spain). Inst. de Fusion Nuclear
Description
Even though general conclusions cannot be derived for all the protection schemes in inertial confinement fusion (ICF) reactors, the feasibility of the ferritic alloy HT-9 as the main component of the first structural wall (FSW) in ICF facilities using thin film Li17Pb83 liquid protection, flowing through porous tubes (INPORT), can be demonstrated as a solution in terms of radiation damage. (author)
Additional details
Publishing Information
- Journal Title
- Laser and Particle Beams
- Journal Volume
- 11
- Journal Issue
- 2
- Journal Page Range
- p. 437-442.
- ISSN
- 0263-0346
- CODEN
- LPBEDA
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 25020587
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- DAMAGING NEUTRON FLUENCE; FERRITE; FIRST WALL; ICF DEVICES; LITHIUM ALLOYS; MATERIALS; RADIATION PROTECTION; RECYCLING; WASTE DISPOSAL
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; IRON ALLOYS; MANAGEMENT; NEUTRON FLUENCE; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; WASTE MANAGEMENT