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This is a preprint of a paper to be presented at the IAEA Specialists' Meeting on Coolant Chemistry, Plateout and Decontamination, December 2-4, 1980, Jiilich, Federal Republic of Germany, and to be published in the Proceedings.

The Peach Bottom Unit N o. 1 Atomic Power Station was the first installation of a High-Temperature Gas-Cooled Reactor (HTGR) in the United States. The plant was successfully operated between March 3 , 1966 (first criticality, Core 1) and October 31, 1974 (end-of-life, Core-2) at which time the plant was shut down for decommissioning. The 40-MW(e) reactor demonstration plant operated very successfully and produced superheated steam at 1000°F and 1450 psig with an overall nuclear steam supply system availability of 88% and gross plant thermal efficiency of 37.2%. Over 1.2 million MW(e)-hr were produced for the Philadelphia Electric Company grid over a lifetime of 1349 equivalent full power days, with a gross plant capacity factor of 74%. Subsequent t o shutdown, the Peach Bottom End-of-Life Program, jointly sponsored by ERDA and EPRI, was initiated. The objective of the program is t o validate specific HTGR design codes and predictions by comparison of observed and predicted physics, thermal, fission product, and materials behavior in Peach Bottom. End-of-Life Program to provide a reference data base for future HTGR evaluations and design verifications.

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