HTGR Knowledge Base

Conference Article: Seismic design, analysis and testing of the HTGR MK-IVA steam generator

Orr, J.D.; Schleicher, R.W.; Tong, K.J. (General Atomic Co., San Diego, CA)

Abstract

The HTGR MK-IVA Steam Generator is a once-through design consisting of two heat transfer bundles, a helical economizer-evaporator-superheater (EES), and a straight tube finishing superheater (STSH) which is located at the longitudinal center of the helical EES. The helically coiled EES bundle support structural design, dynamic analysis, and seismic test program are described.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
IAEA IWGGCR specialists' meeting on gas-cooled reactor seismic design problems and solutions. San Diego, CA (USA). 30 Aug - 1 Sep 1982
International Atomic Energy Agency, Vienna (Austria).
IWGGCR--6, pp:61-74