Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.017 seconds
Baxter, A.M.; Iyer, P.A.
General Atomic Co., San Diego, Calif. (USA)1978
General Atomic Co., San Diego, Calif. (USA)1978
AbstractAbstract
[en] Advanced High Temperature Gas-cooled Reactor (HTGR) design concepts for energy production via gas turbine and process heat applications center on cores generating helium coolant outlet temperatures of up to 10000C (18000F). A preliminary analysis of a large HTGR core using a prismatic fuel with coolant gas core outlet temperatures of 9500C (17400F) is presented. The purpose of this study was to provide detailed core design information in the areas of radial fuel zoning, power distribution, fuel performance, fuel temperatures, and fission product release for a large HTGR core operating under very high temperature conditions to identify potential problem areas and to suggest where improvements could be made in future design work
Primary Subject
Source
Feb 1978; 88 p; Available from NTIS., PC A05/MF A01
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue