History of and prospects for gas-cooled reactors in the United States

Technical Report · Sat May 01 04:00:00 EDT 1982

DOI:https://doi.org/10.2172/5109106· OSTI ID:5109106

Simon, R. H.

The Fort St. Vrain Nuclear Generating Station, which is the only operating HTGR in the United States and which recently achieved 100% power, is described. The report covers the use of helium-cooled reactors for electricity generation, cogeneration of steam for industrial processes and for electric power, and process heat. Three types of reactors are described for electricity generation: the steam cycle HTGR, which is based on Fort St. Vrain; the gas turbine HTGR, which utilizes a direct cycle; and the Gas-Cooled Fast Breeder Reactor (GCFR), which is also based on Fort St. Vrain and which not only would produce electricity but would have the potential to achieve compound system doubling times of fissionable material of under ten years. The HTGR is particularly well suited for the cogeneration of steam and electric power. The cogeneration plant, which has the same nuclear steam supply system as the steam cycle HTGR, is described along with a number of possible industrial applications. The process heat HTGR is being designed to two versions: an 850/sup 0/C core outlet temperature with an intermediate helium loop and a 950/sup 0/C core outlet temperature with a reformer and steam generator in the primary circuit. The technical performance, fuel cycles, safety characteristics, and environmental impact of the HTGR and GCFR are also discussed in the report.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• DOE Contract Number: AT03-76SF70046
• OSTI ID: 5109106
• Report Number(s): GA-A-16637; ON: DE82015390
• Country of Publication: United States
• Language: English

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