Reactor Safety Study Research Articles

Analytic Solutions for Transient Temperature Distributions in Two-Region Nuclear Reactor Fuel Elements

Analytic solutions are developed for the transient temperature distributions in two-region nuclear reactor fuel elements. One region contains a space-independent heat source having an arbitrary time dependence; the other region is source-free. Infinite cylinder and infinite slab geometries are considered, and simplifying assumptions are discussed which reduce the general solutions to simple forms of special interest in reactor safety studies.

Analogue computers and their use in nuclear reactor safety studies

Computational and circuit techniques are described which have been used successfully to study the various aspects of nuclear plant kinetics which are relevant to reactor safety. These include an examination of the overall stability of the system, the effects of coolant pump failure, burst steam lines and control rod maloperation. Particular reference is made to a revolving capacitance storage drum which simulates transport lags in coolant circuits.