Published September 1967 | Version v1
Book Metadata-only

Safety Features of the Hinkley Point B AGR Pressure Vessel and Penetrations

Creators

  • 1. Nuclear Power Group Limited, Radbroke Hall, Knutsford, Cheshire (United Kingdom)

Description

The concrete pressure vessel surrounding an AGR has penetrations through its walls for the gas circulators, steam and feed pipes, control rods and refuelling system and for various reactor services. Retention of the high-pressure gas coolant within the pressure vessel depends on the continuing integrity of these penetrations. The paper describes in detail the large penetrations in the vessel walls of an AGR of the Hinkley Point B type and discusses the criteria governing their design, construction and operation. Arguments are presented which lead to the conclusion that the penetrations, when appropriately designed and constructed, can have sufficient integrity for an AGR to be sited in a densely populated area. (author)

Part of:
Containment And Siting Of Nuclear Power Plants. Proceedings Of The Symposium

Additional details

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (International Atomic Energy Agency (IAEA))
Imprint Title
Containment and Siting of Nuclear Power Plants. Proceedings of a Symposium on the Containment and Siting of Nuclear Power Plants
Imprint Pagination
836 p.
Series
Proceedings Series
Journal Page Range
p. 597-617
ISSN
0074-1884

Conference

Title
Symposium on the Containment and Siting of Nuclear Power Plants
Dates
3-7 Apr 1967
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
44077194
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONCRETES; CONTROL ELEMENTS; GASES; HINKLEY POINT-B REACTOR; PIPES; PRESSURE VESSELS; REACTOR OPERATION; REACTOR SAFETY; RETENTION; STEAM; WALLS
Descriptors DEC
AGR TYPE REACTORS; BUILDING MATERIALS; CARBON DIOXIDE COOLED REACTORS; CONTAINERS; ENRICHED URANIUM REACTORS; FLUIDS; GAS COOLED REACTORS; GCR TYPE REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; TUBES

Optional Information

Notes
9 refs., 8 figs., 1 tab.
Secondary number(s)
IAEA-SM--89/35