Second International Forum on Expert Systems and Computer Simulation in Energy Engineering
DOI: 10.1615/ICHMT.1992.IntForumExpSysCompSimEE
ISBN Print: 978-1-56700-486-1
DYNAMIC BEHAVIOR CALCULATION OF REACTOR POWER AND FUEL TEMPERATURE IN A LARGE PWR POWER PLANT SYSTEM
pages 13.2.1-13.2.5
DOI: 10.1615/ICHMT.1992.IntForumExpSysCompSimEE.460
ABSTRAKT
This work studies the dynamic response of reactor power and fuel temperature in a PWR power plant system. A lumped parameter technique is adopted to compute the aforementioned dynamic variables relating to the safety requirements in nuclear plants. Four simulation incidents are studied: (a)increase in load demand. (b)decrease in reactor coolant flow. (c)decrease in inlet core temperature and (d)control rod ejection. The governing equations derived are solved numerically by the fourth order Runge-Kutta method. The results are reported and discussed in some detail.