Measurement of the Syrian miniature neutron source core average temperature by means of reactivity

A mathematical model has been developed to simulate the dynamic behavior of the Syrian Miniature Neutron Source Reactor. The purpose is to assess and evaluate the core average temperature as a function of the overall reactivity load in the core. The model considers relevant physical phenomena that govern the core such as reactor kinetics, reactivity feedbacks due to coolant temperature and xenon, and thermal hydraulics. Natural convection and point kinetics including the prompt jump and complete mixing approximations were employed. Peak power, reactivity core load, core outlet temperature and other variables are predicted during self-limiting power excursions. Good agreement has been obtained with other comparable studies. Core average temperature was studied a a function of reactivity during reactor operation and transients. An overall rough estimate of core average temperature as a function of reactivity load is presented; hence, a procedure to measure such temperature is suggested. (C) 2002 Elsevier Science Ltd. All rights reserved.