This document presents the reactor structure design and evaluation for a 2 00-Mwe prototype large SGR. The concept of the 1000-Mwe plant and its 200-Mwe prototype plant is completely described in Volumes I and II of NAA-SR-9213, issued in December 1963. Additional analysis and studies completed since that time represent the thermo-mechanical design of the 200-Mwe prototype reactor structure. This document describes the expected operating environment for the 30-yr plant life, treats the steady-state and transient effects on the reactor structure, provides the basis for selection of materials, summarizes results of the mechanical-structural analysis, and describes calandria leak detection and remote maintenance techniques. The results of these studies indicate a highly reliable reactor, conservatively designed to fulfill operating requirements of the 200-Mwe SGR Prototype.
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