HTGR Knowledge Base

Conference Article: Pressure vessel design codes: A review of their applicability to HTGR components at temperatures above 800 deg C

Hughes, P.T. (General Electric Co., Sunnyvale, CA (United States)); Over, H.H. (Kernforschungsanlage Juelich GmbH, IRW, Juelich (Germany)); Bieniussa, K. (Gesellschaft fuer Reaktorsicherheit mbH, Koeln (Germany))

Abstract

The governments of USA and Federal Republic of Germany have approved of cooperation between the two countries in an endeavour to establish structural design code for gas reactor components intended to operate at temperatures exceeding 800 deg C. The basis of existing codes and their applicability to gas reactor component design are reviewed in this paper. This review has raised a number of important questions as to the direct applicability of the present codes. The status of US and FRG cooperative efforts to obtain answers to these questions are presented.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Specialists' meeting on heat exchanging components of gas-cooled reactors Duesseldorf (Germany) 16-19 Apr 1984
International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria)
IWGGCR--9, pp:335-344