Published 1982 | Version v1
Journal article Metadata-only

On radiation plasticity of ceramic nuclear fuel at standard fission densities

Creators

  • 1. AN Uzbekskoj SSR, Tashkent. Inst. Yadernoj Fiziki

Description

The power reactor fuel elements operation conditions are considered. This analysis permits to determine the parameters of testing ceramic nuclear fuel when studying its mechanical properties. The problems of experimental studying mechanical properties of ceramic oxide fuel are as follows: investigation of fuel behaviour at constant-rate deformation; investigation of stress relaxation in the definite temperature range and at initial stresses of 30-80 MPa; creep investigation. In solution of these problems in experimental plants considerable difficulties connected with ensuring the heat removal, decrease of temperature gradients and thermal stresses determination of effective fission density arise

Additional details

Additional titles

Original title (Russian)
О радиационной пластичности керамического ядерного топлива при штатных плотностях делений

Publishing Information

Journal Title
Izv. Akad. Nauk Uzb. SSR, Ser. Fiz.-Mat. Nauk
Journal Issue
no.4
Series
Izv. Akad. Nauk Uzb. SSR, Ser. Fiz.-Mat. Nauk.
ISSN
0131-8012

INIS

Country of Publication
Uzbekistan
Country of Input or Organization
USSR
INIS RN
14783942
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
Descriptors DEI
BURNUP; CERAMICS; CREEP; DEFORMATION; FBR TYPE REACTORS; FUEL ELEMENTS; IRRADIATION DEVICES; NEUTRON FLUX; NUCLEAR FUELS; PHYSICAL RADIATION EFFECTS; PLASTICITY; POWER DENSITY; RESEARCH REACTORS; STRESS RELAXATION; THERMAL STRESSES; URANIUM DIOXIDE; VERY HIGH TEMPERATURE; WWER TYPE REACTORS
Descriptors DEC
ACTINIDE COMPOUNDS; BREEDER REACTORS; CHALCOGENIDES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FUELS; MATERIALS; MECHANICAL PROPERTIES; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; STRESSES; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS