首页> 美国政府科技报告 >DIGITAL COMPUTER STUDY OF NUCLEAR REACTOR THER¬MAL TRANSIENTS DURING STARTUP OF 60-kWe BRAYTON POWER CONVERSION SYSTEM
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DIGITAL COMPUTER STUDY OF NUCLEAR REACTOR THER¬MAL TRANSIENTS DURING STARTUP OF 60-kWe BRAYTON POWER CONVERSION SYSTEM

机译:60kWe布雷顿功率转换系统启动时核反应堆瞬态的数字计算机研究

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摘要

A digital computer study was made of reactor thermal transients during startup of the Brayton power conversion loop of a 60-kWe reactor Brayton power system. A startup procedure requir¬ing the least Brayton system complication was tried first;this procedure caused violations of design limits on key reactor variables. Several modifications of this procedure were then found which caused no design limit violations. These modifications involved (1) using a slower rate of increase in gas flow, (2) increasing the initial reactor power level to make the reactor respond faster, and (3) appropriate reactor control drum manipulation during the startup transient.

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