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Neylan, A.J.; Northup, T.E.
General Atomic Co., San Diego, CA (USA)1982
General Atomic Co., San Diego, CA (USA)1982
AbstractAbstract
[en] Analytical methods for the high-temperature gas-cooled reactor (HTGR) include development, update, verification, documentation, and maintenance of all computer codes for HTGR design and analysis. This paper presents selected nuclear, structural mechanics, seismic, and systems analytical methods related to the HTGR core. This paper also reviews design verification tests in the reactor core, reactor internals, steam generator, and thermal barrier
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Source
May 1982; 10 p; BNES international conference on gas cooled reactors today; Bristol (UK); 20 - 24 Sep 1982; CONF-820915--1; Available from NTIS., PC A02/MF A01 as DE82016251
Record Type
Report
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Conference
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