Published 1981
| Version v1
Journal article
Conceptual design and material consideration on toroidal CTR first wall
Description
An integrated, modular wedge-shaped first wall and blanket system for a toroidal D-T controlled thermonuclear reactor (CTR) is proposed which differs from various concepts of the first wall or first wall and blanket reference designs reported. The candidate materials are selected to meet the probable environment and the required properties of the integrated, modular first wall and blanket systems. The following important areas are analyzed: (1) neutronics and heavy particle bombaramet, (2) structural integrity, (3) heat transfer and corrosion resistance, and (4) energy generation and tritium breeding of the first wall and blanket material(s)
Additional details
Publishing Information
- Journal Title
- Proc. Symp. Eng. Probl. Fusion Res.
- Journal Issue
- p. 1617-1620
- Series
- Proc. Symp. Eng. Probl. Fusion Res.
- ISSN
- 0145-5958
Conference
- Title
- 9. symposium on engineering problems of fusion research.
- Dates
- 26-29 Oct 1981.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14789845
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING BLANKETS; CORROSION; FIRST WALL; HEAT TRANSFER; MATERIALS; MECHANICAL PROPERTIES; MODULAR STRUCTURES; RADIATION EFFECTS; SPECIFICATIONS; SPUTTERING; THERMONUCLEAR REACTORS; TRITIUM
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CHEMICAL REACTIONS; ENERGY TRANSFER; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; THERMONUCLEAR REACTOR WALLS; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- CONF-811040--.