Abstract
Abstract The transient response of a nuclear-reactor system can be extremely difficult to determine by analytical methods. Frequently, recourse must be made to a computational device if a complete description of the system is to be obtained. In this study, an analog computer was employed to investigate the transient behavior of a sodium-cooled, graphite-moderated heterogeneous reactor and its primary-loop heat exchanger. The twofold purpose of the study was to analyze this particular reactor system and to obtain a general evaluation of the errors that result from the simplifying assumptions often made to solve reactor transient problems. The most important result of the study is the demonstration of the inherent short-term stability of this type of reactor and the long-term transient instability that results unless external control is employed.
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