Published 1981 | Version v1
Journal article

Conceptual design and material consideration on toroidal CTR first wall

Creators

  • 1. Iowa State Univ, Ames, USA

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).

Optional Information

Secondary number(s)
CONF-811040--.