Published September 1988 | Version v1
Journal article Metadata-only

Reactor graphite tensile strength

Creators

Description

A method of testing is described for cylindrical graphite samples. Dose dependences of relative change in the ultimate tensile strength of reactor graphite samples are presented for the irradiation temperature range 340-800 K and fluence to 5x1021 neutr/cm2

Additional details

Additional titles

Original title (Russian)
Прочност' реакторного графита при растяжении

Publishing Information

Journal Title
Problemy Prochnosti
Journal Issue
no.9
Series
Probl. Prochn.
ISSN
0556-171X
CODEN
PPCNB

INIS

Country of Publication
Ukraine
Country of Input or Organization
USSR
INIS RN
20029167
Subject category
S36: MATERIALS SCIENCE;
Descriptors DEI
GRAPHITE; HIGH TEMPERATURE; NEUTRON FLUENCE; RADIATION HARDENING; TENSILE PROPERTIES
Descriptors DEC
CARBON; ELEMENTS; HARDENING; MECHANICAL PROPERTIES; NONMETALS; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS