General description of preliminary design of an experimental fusion reactor and the future problems
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
Recently, the studies on plasma physics has progressed rapidly, and promising experimental data emerged successively. Especially expectation mounts high that Tokamak will develop into power reactors. In Japan, the construction of large plasma devices such as JT-60 of JAERI is going to start, and after several years, the studies on plasma physics will come to the end of first stage, then the main research and development will be directed to power reactors. The studies on the design of practical fusion reactors have been in progress since 1973 in JAERI, and the preliminary design is being carried out. The purposes of the preliminary design are the clarification of the concept of the experimental reactor and the requirements for the studies on core plasma, the examination of the problems for developing main components and systems of the reactor, and the development of design technology. The experimental reactor is the quasi-steady reactor of 100 MW fusion reaction output, and the conditions set for the design and the basis of their setting are explained. The outline of the design, namely core plasma, blankets, superconductive magnets and the shielding with them, vacuum wall, neutral particle injection heating device, core fuel supply and exhaust system, and others, is described. In case of scale-up the reactor structural material which can withstand neutron damage must be developed. (Kako, I.)
Additional details
Publishing Information
- Journal Title
- Genshiryoku Kogyo
- Journal Volume
- 22
- Journal Issue
- 8
- Series
- Genshiryoku Kogyo.
- Journal Page Range
- 33-42
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 8319822
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BEAM INJECTION HEATING; BREEDING BLANKETS; CRYOPUMPS; IMPURITIES; PLANNING; PLASMA; REACTOR COOLING SYSTEMS; REACTOR MAINTENANCE; REPAIR; SHIELDING; SUPERCONDUCTING MAGNETS; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS
- Descriptors DEC
- COOLING SYSTEMS; ELECTRICAL EQUIPMENT; ELECTROMAGNETS; HEATING; MAGNETS; MAINTENANCE; PLASMA HEATING; PUMPS; REACTOR COMPONENTS; SUPERCONDUCTING DEVICES; VACUUM PUMPS