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UK fast reactor components - sodium removal decontamination and requalification

Abstract

Over the past two decades extensive experience on sodium removal techniques has been gained at the UKAEA's Dounreay Nuclear Establishment from both the Dounreay Fact Reactor (DFR) and the Prototype Fast Reactor (PFR). This experience has created confidence that complex components can be cleaned of sodium, maintenance or repair operations carried out, and the components successfully re-used. Part 2 of the paper, which describes recent operations associated with the PFR, demonstrates the background to these views. This past and continuing experience is being used in forming the basis of the plant to be provided for sodium removal, decontamination and requalification of components in the UK's future commercial fast reactors. Further improvements in techniques and in component designs can be expected in the course of the next few years. Consequently UK philosophy and approach with respect to maintenance and repair operations is sufficiently flexible to enable relevant improvements to be incorporated into the next scheduled fast reactor - the Commercial Demonstration Fast Reactor (CUR). This paper summarises the factors which are being taken into consideration in this continuously advancing field.
Authors:
Donaldson, D M; [1]  Bray, J A; Newson, I H [2] 
  1. FRDD, UKAEA, Risley (United Kingdom)
  2. UKAEA, Dounreay Nuclear Power Establishment, Thurso (United Kingdom)
Publication Date:
Aug 01, 1978
Product Type:
Conference
Report Number:
IWGFR-23
Reference Number:
EDB-01:030718
Resource Relation:
Conference: IAEA-IWGFR specialists meeting on sodium removal and decontamination, Richland, WA (United States), 14-16 Feb 1978; Other Information: 7 refs, 14 figs, 2 tabs; PBD: Aug 1978; Related Information: In: Specialists meeting on sodium removal and decontamination. Summary report, 213 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CDFR REACTOR; CLEANING; DECONTAMINATION; DFR REACTOR; PFR REACTOR; REACTOR COMPONENTS; SODIUM
OSTI ID:
20146275
Research Organizations:
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0100479011797
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 108-123
Announcement Date:

Citation Formats

Donaldson, D M, Bray, J A, and Newson, I H. UK fast reactor components - sodium removal decontamination and requalification. IAEA: N. p., 1978. Web.
Donaldson, D M, Bray, J A, & Newson, I H. UK fast reactor components - sodium removal decontamination and requalification. IAEA.
Donaldson, D M, Bray, J A, and Newson, I H. 1978. "UK fast reactor components - sodium removal decontamination and requalification." IAEA.
@misc{etde_20146275,
title = {UK fast reactor components - sodium removal decontamination and requalification}
author = {Donaldson, D M, Bray, J A, and Newson, I H}
abstractNote = {Over the past two decades extensive experience on sodium removal techniques has been gained at the UKAEA's Dounreay Nuclear Establishment from both the Dounreay Fact Reactor (DFR) and the Prototype Fast Reactor (PFR). This experience has created confidence that complex components can be cleaned of sodium, maintenance or repair operations carried out, and the components successfully re-used. Part 2 of the paper, which describes recent operations associated with the PFR, demonstrates the background to these views. This past and continuing experience is being used in forming the basis of the plant to be provided for sodium removal, decontamination and requalification of components in the UK's future commercial fast reactors. Further improvements in techniques and in component designs can be expected in the course of the next few years. Consequently UK philosophy and approach with respect to maintenance and repair operations is sufficiently flexible to enable relevant improvements to be incorporated into the next scheduled fast reactor - the Commercial Demonstration Fast Reactor (CUR). This paper summarises the factors which are being taken into consideration in this continuously advancing field.}
place = {IAEA}
year = {1978}
month = {Aug}
}