U. S. /FRG joint pebble bed reactor evaluation. Final report, fiscal year 1977

Technical Report · Sat Oct 01 04:00:00 EDT 1977

DOI:https://doi.org/10.2172/5356547· OSTI ID:5356547

The scope of the program has been to develop technical, economic, and program information in support of decisions and planning by DOE regarding thermal gas-cooled reactor (TGR) development in the U.S. and cooperative international TGR programs. Particular emphasis has been placed on technical review of the large pebble bed high-temperature gas-cooled reactor (HTR) concept under development by the Federal Republic of Germany (FRG). A matrix of decision input information has been prepared. This information is summarized in this report and includes comparison information for selected energy alternatives. Technical review of the large pebble bed reactor concept emphasizes the core and related systems, considering that other HTR plant features are similar for either prismatic or pebble bed fuel cores. A review of the prestressed cast iron pressure vessel (PCIV) concept is reported along with safety and licensing considerations for potential U.S. licensing of an FRG-developed HTR plant.

• Research Organization: General Atomic Co., San Diego, Calif. (USA)
• OSTI ID: 5356547
• Report Number(s): GA-A-14611
• Country of Publication: United States
• Language: English

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COMPARATIVE EVALUATIONS
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