Fusion materials studies and technological experiments in test thermonuclear reactor-tokamak
Creators
- 1. Scientific Research and Design Inst. of Power Engineering, Moscow (USSR)
Description
Extensive studies of materials (strength, radiation resistance, reliability and safety) should be made to substantiate designs during the initial stage of R and D and the choice of the final version for the design of the blanket and energy conversion system. It is evident that those experimental devices which are available or planned are not capable of simulating effects on the OTR blanket units (high neutron flux, strong electromagnetic fields, stresses due to coolant pressure at operating temperature and own weight, plasma effects, etc.). Therefore, in OTR design, constructive decisions should be taken on the use of the tokamak OTR as a unique experimental device for real full-scale tests of construction, uranium, lithium and protective materials (antidiffusion coatings for radiation safety, etc.) intended for long term reliable and safe operation in future commercial fusion reactors. In the paper, consideration is given to some experimental devices intended for the study of the physical and mechanical properties of materials under loads typical of blanket operation; research into the mutual compatibility of construction materials, with coolant and operating materials; the study of the efficiency and reliability of material coatings; and the determination of optimal operating temperature ranges for materials, etc. (author). 2 refs, 5 figs
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna (Austria)
- ISBN
- 92-0-131287-3
- Imprint Title
- Fusion reactor design and technology 1986
- Imprint Pagination
- 523 p.
- Series
- Panel proceedings series.
- Journal Page Range
- v. 2 p. 359-370.
Conference
- Title
- 4. technical committee meeting and workshop on fusion reactor design and technology.
- Dates
- 26 May - 6 Jun 1986.
- Place
- Yalta (USSR).
INIS
- Country of Publication
- Austria
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 19042919
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING BLANKETS; EXPERIMENTAL CHANNELS; FIRST WALL; IRRADIATION CAPSULES; PHYSICAL RADIATION EFFECTS; THERMONUCLEAR REACTOR MATERIAL; TRITIUM RECOVERY
- Descriptors DEC
- MATERIALS; RADIATION EFFECTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; THERMONUCLEAR REACTOR WALLS
Optional Information
- Secondary number(s)
- IAEA-TC--392.3/57.