Published July 1988
| Version v1
Journal article
Testing of the nuclear in-vessel components
Creators
- 1. The NET Team, c/o Max-Planck-Institut fur Plasmaphysik, Boltzmannstrasse 2, D-8046 Garching bei Munchen (Germany, F.R.)
Description
The development and testing of the nuclear in-vessel components in fusion reactor-relevant conditions is one of the major objectives of the Next European Torus (NET). The scope of nuclear testing in NET, the testing requirements, and program for the various breeding blanket concepts are defined and discussed with respect to thermal behavior, heat recovery, and tritium recovery. The relevance of NET testing for high neutron wall loads is also analyzed
Additional details
Publishing Information
- Journal Title
- Fusion Technology
- Journal Volume
- 14
- Journal Issue
- 1
- Series
- Fusion Technol.
- Journal Page Range
- 187-196
- ISSN
- 0748-1896
- CODEN
- FUSTE
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20031374
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BREEDING BLANKETS; DYNAMIC LOADS; FIRST WALL; HEAT RECOVERY; NET TOKAMAK; NEUTRONS; PERFORMANCE TESTING; REACTOR COMPONENTS; RESEARCH PROGRAMS; STEADY-STATE FUSION REACTORS; THERMAL CYCLING; TRITIUM RECOVERY
- Descriptors DEC
- BARYONS; CLOSED PLASMA DEVICES; ELEMENTARY PARTICLES; ENERGY RECOVERY; FERMIONS; HADRONS; NUCLEONS; TESTING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES