Published 1969 | Version v1
Conference paper

Safety of the SGHWR prototype

  • 1. United Kingdom Atomic Energy Authority, Risley, Cheshire, United Kingdom

Description

The paper opens by reviewing the approach to safety considered in the UK. The vented containment system of the prototype SGHWR is described along with development of the concept for future reactors using enriched fuel. An outline is given of the development work carried out on the release, fate and clean-up of fission products, the propagation of failures, fuel can performance at high temperature and containment design. Reference is made to emergency cooling and the provisions for inspection and testing. The method of safety assessment and supporting analytical work are discussed and the paper ends with a statement on the results of fission product release assessments for the Prototype reactor.

Part of:
Steam generating and other heavy water reactors

Additional details

Publishing Information

Imprint Pagination
p. 143-151

Conference

Title
Steam generating and other heavy water reactors
Dates
14-16 May 1968
Place
London, United Kingdom
Session
C

Optional Information