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U.S. Department of Energy
Office of Scientific and Technical Information

HTGR-process steam/cogeneration and HTGR-steam cycle program. Semiannual report, October 1, 1979-March 31, 1980

Technical Report ·
DOI:https://doi.org/10.2172/6808910· OSTI ID:6808910
Progress in the design of an 1170-MW(t) High-Temperature Gas-Cooled Reactor (HTGR) Nuclear Steam Supply (NSS) is described. This NSS can integrate favorably into present petrochemical and primary metal process industries, heavy oil recovery operations, and future shale oil recovery and synfuel processes. The economics appear especially attractive in comparison with alternative coal-fired steam generation. Cost estimates for central station power-generating 2240- and 3360-MW(t) HTGR-Steam Cycle (HTGR-SC) plants are updated. The 2240-MW(t) HTGR-SC is treated to a probabilistic risk evaluation. Compared with the earlier 3000-MW(t) design, the results predict a slightly increased risk of core heatup, owing to the result of eliminating the capability of the boiler feed pump to operate at atmospheric backpressure. The differences in risk, however, are within the calculational uncertainties. Preliminary results of the ranking of safety enhancement features for the 1170-MW(t) HTGR indicate that the following modifications offer the most promise: (1) capability for main loop rundown, (2) natural circulation core auxiliary cooling, and (3) PCRV blowdown capability through the helium purification system to minimize activity release during some core heatups.
Research Organization:
General Atomic Co., San Diego, CA (USA)
DOE Contract Number:
AT03-76ET35301
OSTI ID:
6808910
Report Number(s):
GA-A-16057
Country of Publication:
United States
Language:
English