Abstract
The first prototype high temperature gas cooled reactor (HTGR) was successfully developed, designed, built, tested, operated and decommissioned between 1958 and 1978 as part of a cooperative program between the Atomic Energy Commission and several industries participating as follows: Philadelphia Electric Company, owner-operator together with High Temperature Reactor Development Associates; General Atomic Company, conceptual development design and NSSS supplier; and Bechtel Corporation, architect engineer. Developed improvements included: the successful replacement of austenitic stainless steel steam generator tubes that suffered chloride stress corrosion with Incoloy tubes; and the replacement of purged fuel elements, consisting of uranium and thorium carbide particles coated with a dense pyrocarbon in a graphite matrix, with irradiation resistant double coated particles that retained fission products and yielded no more than 0.5 Ci radioactivity in the continuously purified helium coolant. In commercial operation, the plant produced steam at 1000F and 1450 psig and generated power with a thermal efficiency of 37% and 88% availability, excluding R and D programs and planned shutdowns, from July 1967 to October 1974. Termination of operation and decommissioning proceeded according to approved plans.
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