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.
Capsule P13T was the ninth in a series of irradiation tests conducted under the Department of Energy (DOE)-sponsored High-Temperature Gas-Cooled Reactor (HTGR) Fuels and Core Development Program. It was the first accelerated irradiation test of large-diameter graphite-fuel bodies containing cure-in-place fuel rods not removed prior to irradiation and irradiated to peak large high-temperature gas-cooled reactor (LHTGR) fast fluences. The primary purpose of this test was to evaluate the irradiation performance of the integral bodies and cured-in-place fuel rods and to compare the irradiation and thermal performance of dense melted high-enriched uranium (HEU) UC2-TRISO and HEU-UCO weak acid resin (WAR) TRISO fissile fuel particles. A secondary purpose of this test was to support the LHTGR fuel product specifications and to provide irradiation data for fuel performance models used in design evaluations. Seven TRISO UC2, one TRISO UCO-WAR, and nine BISO-Tho2 coated-particle batches were used in the 36 fuel rods. diated two types of near-isotropic graphite fuel bodies. The capsule was irradiated 363.4 equivalent full power days in the Oak Ridge Research Reactor (ORR) at Oak Ridge National Laboratory (ORNL).
NOTICE m i r report was Prepared 1 6 an account of work sponsored by the United States Gwernment. Nelther L e United Stater nor the United Stater Energy Research and Development Addmstration, nor any of their employees, nor any o f their c~n t r a~t~r i , subcontractors, or their employees. makes any W.IIIPII~Y, crpreu or implied, or auumes any I+ liability or rcspondbilily for the accuracy, completeness proars discloud. or representr that its u v would not infringe privately owned rights.
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