Published 1978 | Version v1
Book Metadata-only

Practical design of internal shields for AGRs and the demonstration of their effectiveness

Creators

  • 1. Nuclear Power Co. (Risley) Ltd. (UK)
  • 2. Nuclear Power Co. (Whetstone) Ltd. (UK)

Description

This paper describes the practical design of the shielding which is provided inside the concrete pressure vessels on Advanced Gas Cooled Reactors (AGRs). The arrangement of internal shields adopted for the Hinkley Point B and Hartlepool reactors is described, since they serve as examples of the two basic vessel designs currently employed. The latest proposals for the current AGR design are also included. Practical design considerations and the design criteria involved are discussed and the effectiveness of design predictions is demonstrated by the results of a set of shielding experiments performed on the Hinkley reactor. (author)

Additional details

Publishing Information

Publisher
British Nuclear Energy Society.
Imprint Place
London
ISBN
0 7277 0072 3
Imprint Title
Radiation protection in nuclear power plants and the fuel cycle. Volume 1
Journal Page Range
p. 91-100.

Conference

Title
Conference on radiation protection in nuclear power plants and the fuel cycle.
Dates
27 Nov - 1 Dec 1978.
Place
Bristol, UK.

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
11509053
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AGR TYPE REACTORS; CONCRETES; HARTLEPOOL REACTOR; HINKLEY POINT-B REACTOR; PERFORMANCE; PRESSURE VESSELS; SHIELDING; SHIELDS; SPECIFICATIONS
Descriptors DEC
BUILDING MATERIALS; CARBON DIOXIDE COOLED REACTORS; CONTAINERS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS