Published May 1987 | Version v1
Report

Some considerations on selection criteria for graphites as fusion materials

Creators

  • 1. Japan Atomic Energy Research Institute

Description

Some considerations are made on the selection criteria for graphite materials when they are used for the fusion reactor components. The selection criteria are examined considering that the graphite might fracture due to internal stresses. The internal stresses consist of a thermal stress based on temperature gradient in the components and irradiation-induced stress associated with dimensional changes due to neutron irradiation. It is stressed that the irradiation-induced stress is particularly important. There it may be impossible for the graphite to fracture if a stress generated is smaller than the fracture stress and a stress intensity factor or a J-integral value which controls initiation and extension of cracks is smaller than the respective fracture toughness value. From such viewpoints the selection criteria for graphite materials are examined and the present status of the data base on properties which are considered to be significant is reviewed. As a result, the data group which should be intensively obtained are defined

Additional details

Publishing Information

Imprint Title
Proceedings of the Japan-US Workshop P-92 on plasma material interaction/high heat flux data needs for the next step ignition and steady state devices
Journal Page Range
p. 411-423.
Report number
IPPJ-AM--50

Conference

Title
Japan/US workshop P-92 on plasma material interaction/high heat flux data needs for the next step ignition and steady state devices.
Dates
26-30 Jan 1987.
Place
Nagoya (Japan).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19056917
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
EXPERIMENTAL DATA; FRACTURE PROPERTIES; GRAPHITE; IRRADIATION; MATERIALS TESTING; NEUTRON FLUENCE; RADIATION EFFECTS; TEMPERATURE DEPENDENCE; THERMAL STRESSES; THERMONUCLEAR REACTORS; YOUNG MODULUS
Descriptors DEC
CARBON; DATA; ELEMENTS; INFORMATION; MECHANICAL PROPERTIES; NONMETALS; NUMERICAL DATA; STRESSES; TESTING