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.
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
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AGR TYPE REACTORS; CONTAINMENT; CONTAINMENT BUILDINGS; CONTAINMENT SYSTEMS; ECCS; FAILURES; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL CANS; FUEL ELEMENTS; HTGR TYPE REACTORS; INSPECTION; REACTOR SAFETY; SAFETY ANALYSIS; UNITED KINGDOM; VENTS
- Descriptors DEC
- BUILDINGS; CONTAINMENT; DEVELOPED COUNTRIES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EUROPE; GAS COOLED REACTORS; GCR TYPE REACTORS; GRAPHITE MODERATED REACTORS; ISOTOPES; MATERIALS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; WESTERN EUROPE