SBWR reactor system description and development status

The design of the Simplified Boiling Water Reactor (SBWR) represents a complete design fijr a nominal 600 MWe power plant. The rated thoina] output of the reactor core is 2000 MWt, and the rated NSSS thermal output is 1996.1 MWth. The SBWR incorporates innovative, yet proven, concq ts to fiirther amplify an inherently simple direct cycle nuclear plant. The features selected are all proven concepts in large nuclear power plants. 

The principal design criteria governing a SBWR Standard Plant are presented in two ways. First, the criteria are classified as applicable to either a power generation function or a safety-related function. Second, they are grouped according to system. Some significant design criteria are listed below. 

The plant is designed to produce electricity from a turbine generator unit using steam generated in the reactor. 

Heat removal systems are provided with sufficient capacity and operational adequacy to remove heat generated in the reactor core for the full range of normal operational conditions and abnormal operational transients. Backup heat removal systems are provided to remove decay heat generated in the core under circumstances wherein the normal operational heat removal systems become inoperative. The capacity of such systems is adequate to prevent fuel cladding damage. 

The fuel cladding, in conjunction with other plant systems, is designed to retain integrity so that the consequences of any failures are within acceptable limits throughout the range of normal operational conditions and abnormal operational transients for the design life of the fuel. 

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SBWR REACTOR SYSTEM DESCRIPTION AND DEVELOPMENT STATUS 5.3.1. Basic objectives and features... 

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