Journal
ANNALS OF NUCLEAR ENERGY
Volume 28, Issue 10, Pages 1019-1031Publisher
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/S0306-4549(00)00104-3
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Transient heat transfer in a nuclear fuel rod is modelled by an improved lumped parameter approach. Hermite approximation for integration is used to obtain the average fuel and cladding temperatures in the radial direction. Thermohydraulic behaviour of a pressurized water reactor (PWR) during reactivity insertion and partial loss-of-flow is simulated by using a simplified mathematical model of reactor core and primary coolant. Transient temperature response of fuel, cladding and coolant is analysed. (C) 2001 Elsevier Science Ltd. All rights reserved.
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