Published 1987 | Version v1
Book

Fusion materials studies and technological experiments in test thermonuclear reactor-tokamak

  • 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

Part of:
Fusion reactor design and technology 1986. V.2

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.