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Conference Article: The evaluation of occupational exposure on a commercial advanced gas-cooled reactor

Dawson, J.W. (Central Electricity Generating Board, Barnwood (UK). Generation Development and Construction Div.); Youell, F.P. (National Nuclear Corp. Ltd., Knutsford (UK)); Edwards, J. (Hinkley Point 'B' Power Station, Bridgewater (UK))

Abstract

The fundamental principle governing the radiological design of Nuclear Power Stations in the United Kingdom is that radiation exposures to Station operators and to members of the public should be as low as reasonably practicable and consistent with any overriding legislative requirements. To ensure that any Station can be operated in compliance with this principle, the UK Generating Boards have specified design target dose limits for Station staff. This Paper considers the evaluation of operator exposure and its assessment against these design target dose limits for the latest Commercial Advanced Gas Cooled Reactor (CAGR) to be built for the Central Electricity Generating Board (CEGB) on the Heysham Site. The Paper begins by giving the design target dose limits, outlines the details of the dose budgeting procedure adopted at an early design stage by the Station Designers and by the Utilities, and defines the measures available and incorporated into the design with the aims of reducing exposure. The Paper includes the estimate of operator exposure for Heysham II, it considers those aspects of the design giving rise to greatest exposure and shows that the design target dose limits should be achieved. The Paper also gives current levels of operator exposure from Hinkley Point 'B' Power Station which is the CEGB's first operational CAGR. Where possible, the Heysham II estimates are evaluated against this operating experience.

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key words: agr type reactors; dose commitments; dose limits; economics; occupations; personnel dosimetry; personnel monitoring; radiation doses; reactor maintenance; reactor operation; specifications; dosimetry; enriched uranium reactors; gas cooled reactors; graphite moderated reactors; maintenance; monitoring; operation; radiation monitoring; reactors; safety standards
Reference:
Specialists' meeting on safety and accident analysis for gas-cooled reactors. Oak Ridge, TN (USA). 13-15 May 1985
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--358, pp:47-60