SYMPOSIA PAPER Published: 01 January 1982
STP34405S

The U.K. Fast Reactor Materials Programme

Source

The development of sodium cooled fast breeder reactors in the U.K. is briefly reviewed and the points of similarity and of difference in the design and operating conditions of the prototype and commercial demonstration reactors established. The materials selected or under development for fuel element and structural component applications in these reactors are defined and the requirements for achieving high fuel burn-up and for safe and reliable reactor operation discussed. The programmes being implemented to provide the materials data necessary to endorse the requirements are summarised.

Author Information

Harries, DR
Metallurgy Division, AERE, Harwell, Didcot, Oxon
Standring, J
Springfields Nuclear Power Development Laboratories, Salwick, Preston, Lancs
Barnes, WD
National Nuclear Corporation, Risley, Warrington, Cheshire
Lloyd, GJ
Risley Nuclear Power Development Laboratories, Risley, Warrington, Cheshire
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Details
Developed by Committee: E10
Pages: 1197–1217
DOI: 10.1520/STP34405S
ISBN-EB: 978-0-8031-4846-8
ISBN-13: 978-0-8031-0753-3