Prestressed-Concrete Reactor Vessel (PCRV) Design-Concept Study for Small HTGR Steam-Cycle Plant

摘要

A study was performed to identify a prestressed-concrete reactor vessel (PCRV) concept for a high-temperature gas-cooled reactor (HTGR) steam-cycle plant rated on the order of 100 MW(e). The selected configuration, considered optimum for a small HTGR, is based on a single-cavity approach and uses technology and experience gained from the design, construction, and operation of the PCRV for the Fort St. Vrain nuclear generating station in the USA. A feature inherent in the HTGR nuclear-heat-source design, and in concert with enhanced safety goals, is the ability to remove decay heat by passive means (i.e., natural circulation). The use of a PCRV, in conjunction with a reactor core of small thermal rating, and passive cooling capability, even under the most extreme conditions, results in a plant with benign characteristics that can be classified as super-safe. (ERA citation 08:040751)