Published 1979 | Version v1
Miscellaneous Metadata-only

Resistance to rupture in uranium-graphite reactor channels

Creators

Description

.A stress-deformation diagram of the alloy tested at temperatures up to 300 deg C and irradiated by 8x1021 n/cm2 fluence has been built up in order to determine conditions of total rupture of the reactor fuel channel tube made of the Zr-2.5% Nb alloy. It has been established that in investigated temperature and neutron fluence ranges critical dimensions of cracks are minimum at the temperature of 300 deg C and during irradiation by the fluence of 3.8x1021 n/cm2. The diagram has revealed that total rupture of the zirconium fuel channel tube is practically impossible due to too great critical dimensions of defects necessary for the rupture realization

Additional details

Additional titles

Original title (Russian)
Сопротивление разрушению труб технологических каналов уран-графитовых реакторов

Publishing Information

Imprint Title
Physics and mechanics of deformation and destruction. No. 6
Journal Page Range
p. 25-32.
Report number
INIS-mf--6413

INIS

Country of Publication
USSR
Country of Input or Organization
USSR
INIS RN
12604672
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BELOYARSK-1 REACTOR; CRACKS; HIGH TEMPERATURE; HYDRIDATION; NIOBIUM ALLOYS; PHYSICAL RADIATION EFFECTS; REACTOR CHANNELS; TEMPERATURE DEPENDENCE; TENSILE PROPERTIES; ZIRCONIUM BASE ALLOYS
Descriptors DEC
ALLOYS; CHEMICAL REACTIONS; ENRICHED URANIUM REACTORS; GRAPHITE MODERATED REACTORS; LWGR TYPE REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; ZIRCONIUM ALLOYS

Optional Information

Notes
5 refs.; 4 figs.; 3 tabs. Imprint:Fizika i mekhanika deformatsii i razrusheniya. Vypusk 6.