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ISSN Online: 2377-424X

ISBN Print: 0-89116-299-2

International Heat Transfer Conference 7
September, 6-10, 1982, Munich, Germany

NUMEL-M: A COMPUTER CODE TO MODEL THE TRANSIENT RESPONSE OF A DRUM-TYPE STEAM GENERATOR

Get access (open in a dialog) DOI: 10.1615/IHTC7.2320
pages 325-330

Sinopsis

The CEGB nuclear power stations of the Magnox design have boilers of the drum/recirculation type. This paper describes a first stage development of a computer code to quantify boiler operational safety margins which are currently assessed using a grossly pessimistic approach. The model provides a one dimensional representation of the economiser, evaporator and superheater heat exchanger banks of a steam generator unit coupled via models of the steam drum, circulating pump and interconnecting pipework. The model equations are solved using an extension of the semi-1inearisation technique previously adopted in the NUMEL code for once-through AGR (Advanced Gas-cooled Reactor) boilers. The acquisition is described of validation data from plant tests carried out on the Windscale AGR Power Station, which is a prototype AGR fitted with drum/recirculation type steam generator units. Program predictions are compared with data recorded during reactor transients producing temperature and flow perturbations of the carbon dioxide primary flow to these units.