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Irradiation-induced creep in fuel compacts for high-temperature reactor applications

Abstract

Restrained shrinkage experiments at neutron fluences up to 3 x 10/sup 21/ n cm/sup -2/ DNE in the temperature range 600 to 1200/sup 0/C were performed on three different dummy coated-particle fuel compacts in the high-flux reactor at Petten. The data were evaluated to obtain the steady-state radiation creep coefficient of the compacts. It was found that, for the materials investigated, the creep coefficient is temperature dependent, but no clear relationship with Young's modulus could be established. Under certain conditions this irradiation-induced plasticity influences the elastic properties, with the concomitant increase of the creep coefficient. This effect coincides with the formation and further opening up of cracks due to stresses caused by irradiation-induced shrinkage of matrix material.
Authors:
Veringa, H; Blackstone, R; [1]  Loelgen, R
  1. Stichting Energieonderzoek Centrum Nederland, Petten
Publication Date:
Jan 01, 1977
Product Type:
Conference
Reference Number:
AIX-09-370235; ERA-03-039285; EDB-78-077905
Resource Relation:
Journal Name: High Temp. - High Pressures; (United Kingdom); Journal Volume: 9:2; Conference: 2. international carbon conference 'Carbon '76', Baden-Baden, Germany, F.R., 27 Jun - 2 Jul 1976
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 MATERIALS SCIENCE; DISPERSION NUCLEAR FUELS; PHYSICAL RADIATION EFFECTS; COATED FUEL PARTICLES; COMPACTS; CRACKS; CREEP; DAMAGING NEUTRON FLUENCE; HFR REACTOR; HIGH TEMPERATURE; MATRIX MATERIALS; PLASTICITY; STRESSES; TEMPERATURE DEPENDENCE; VERY HIGH TEMPERATURE; YOUNG MODULUS; ELASTICITY; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL PARTICLES; FUELS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; MECHANICAL PROPERTIES; NEUTRON FLUENCE; NUCLEAR FUELS; RADIATION EFFECTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID FUELS; TANK TYPE REACTORS; TENSILE PROPERTIES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 050700* - Nuclear Fuels- Fuels Production & Properties; 360206 - Ceramics, Cermets, & Refractories- Radiation Effects
OSTI ID:
5031341
Country of Origin:
United Kingdom
Language:
English
Other Identifying Numbers:
Journal ID: CODEN: HTHPA
Submitting Site:
INIS
Size:
Pages: 163-167
Announcement Date:

Citation Formats

Veringa, H, Blackstone, R, and Loelgen, R. Irradiation-induced creep in fuel compacts for high-temperature reactor applications. United Kingdom: N. p., 1977. Web.
Veringa, H, Blackstone, R, & Loelgen, R. Irradiation-induced creep in fuel compacts for high-temperature reactor applications. United Kingdom.
Veringa, H, Blackstone, R, and Loelgen, R. 1977. "Irradiation-induced creep in fuel compacts for high-temperature reactor applications." United Kingdom.
@misc{etde_5031341,
title = {Irradiation-induced creep in fuel compacts for high-temperature reactor applications}
author = {Veringa, H, Blackstone, R, and Loelgen, R}
abstractNote = {Restrained shrinkage experiments at neutron fluences up to 3 x 10/sup 21/ n cm/sup -2/ DNE in the temperature range 600 to 1200/sup 0/C were performed on three different dummy coated-particle fuel compacts in the high-flux reactor at Petten. The data were evaluated to obtain the steady-state radiation creep coefficient of the compacts. It was found that, for the materials investigated, the creep coefficient is temperature dependent, but no clear relationship with Young's modulus could be established. Under certain conditions this irradiation-induced plasticity influences the elastic properties, with the concomitant increase of the creep coefficient. This effect coincides with the formation and further opening up of cracks due to stresses caused by irradiation-induced shrinkage of matrix material.}
journal = {High Temp. - High Pressures; (United Kingdom)}
volume = {9:2}
place = {United Kingdom}
year = {1977}
month = {Jan}
}