Abonnement à la biblothèque: Guest
Second International Forum on Expert Systems and Computer Simulation in Energy Engineering
March, 17-20, 1992, Erlangen, Germany

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
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RÉSUMÉ

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.

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