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UK experience on fuel and cladding interaction in oxide fuels

Abstract

The occurrence of fuel cladding interactions in fast reactor fuels has been observed in UK irradiations over a period of years. Chemical incompatibility between fuel and clad represents a potential source of failure and has, on this account, been studied using a variety of techniques. The principal fuel of interest to the UK for fast reactor application is mixed uranium plutonium oxide clad in stainless steel and it is in this field that the majority of work has been concentrated. Some consideration has been given to carbide fuels, because of their application as an advanced fuel. This experience is described in the accompanying paper. Several complementary initiatives have been followed to investigate the interactions in oxide fuel. The principal source of experimental information is from the experimental fuel irradiation programme in the Dounreay Fast Reactor (DFR). Supporting information has been obtained from irradiation programmes in Materials Testing Reactors (MTR). Conditions approaching those in a fast reactor are obtained and the effects of specific variables have been examined in specifically designed experiments. Out-of-reactor experiments have been used to determine the limits of fuel and cladding compatibility and also to give indications of corrosion The observations from all experiments have been examined  More>>
Authors:
Batey, W; [1]  Findlay, J R [2] 
  1. Dounreay Experimental Reactor Establishment, Thurso, Caithness (United Kingdom)
  2. AERE, Harwell, Didcot, Oxon (United Kingdom)
Publication Date:
Apr 01, 1977
Product Type:
Conference
Report Number:
IWGFR-16
Reference Number:
EDB-01:020725
Resource Relation:
Conference: IAEA-IWGFR technical committee meeting on fuel and cladding interaction, Tokyo (Japan), 21-25 Feb 1977; Other Information: 9 refs, 3 figs, 4 tabs; PBD: Apr 1977; Related Information: In: Technical committee meeting on fuel and cladding interaction. Summary report, 208 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BURNUP; CORROSION; DFR REACTOR; FAILURES; FAST REACTORS; FUEL-CLADDING INTERACTIONS; MIXED OXIDE FUELS; MTR REACTOR; THERMODYNAMICS
OSTI ID:
20137472
Research Organizations:
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0100198006567
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 97-103
Announcement Date:
Mar 02, 2001

Citation Formats

Batey, W, and Findlay, J R. UK experience on fuel and cladding interaction in oxide fuels. IAEA: N. p., 1977. Web.
Batey, W, & Findlay, J R. UK experience on fuel and cladding interaction in oxide fuels. IAEA.
Batey, W, and Findlay, J R. 1977. "UK experience on fuel and cladding interaction in oxide fuels." IAEA.
@misc{etde_20137472,
title = {UK experience on fuel and cladding interaction in oxide fuels}
author = {Batey, W, and Findlay, J R}
abstractNote = {The occurrence of fuel cladding interactions in fast reactor fuels has been observed in UK irradiations over a period of years. Chemical incompatibility between fuel and clad represents a potential source of failure and has, on this account, been studied using a variety of techniques. The principal fuel of interest to the UK for fast reactor application is mixed uranium plutonium oxide clad in stainless steel and it is in this field that the majority of work has been concentrated. Some consideration has been given to carbide fuels, because of their application as an advanced fuel. This experience is described in the accompanying paper. Several complementary initiatives have been followed to investigate the interactions in oxide fuel. The principal source of experimental information is from the experimental fuel irradiation programme in the Dounreay Fast Reactor (DFR). Supporting information has been obtained from irradiation programmes in Materials Testing Reactors (MTR). Conditions approaching those in a fast reactor are obtained and the effects of specific variables have been examined in specifically designed experiments. Out-of-reactor experiments have been used to determine the limits of fuel and cladding compatibility and also to give indications of corrosion The observations from all experiments have been examined in the light of thermo-dynamic predictions of fuel behaviour to assess the relative significance of various observations and operating conditions. An experimental programme to control and limit the interactions in oxide fuel is being followed.}
place = {IAEA}
year = {1977}
month = {Apr}
}