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Development of Computer Models for Fuel Element Behaviour in Water Reactors. Survey Report of a CO-Ordinated Research Programme on the Development of Computer Models for Fuel Element Behaviour in Water Reactors

机译:水反应堆燃料元件行为计算机模型的开发。关于水反应堆燃料元件行为计算机模型开发的共同研究计划调查报告

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Description of fuel behaviour during normal operation transients and accident conditions has always represented a most challenging and important problem. Reliable predictions constitute a basic demand for safety based calculations, for design purposes and for fuel performance. Therefore, computer codes based on deterministic and probabilistic models were developed. Possibility of comprehensive descriptions of the phenomena is precluded in view of the great number of individual processes, involving physical, chemical, thermohydraulical and mechanical parameters, to be considered in a wide range of situations. In case of fast thermal transients predictive capability is limited by the kinetics of evolution of the system and its eventual dynamic behaviour. Evidently, probabilistic approaches are also limited by the sparcity and limited breadth of the impirical data base. Code predictions have to be evaluated against power reactor data, results from simulation experiments and, if possible, include cross validation of different codes and validation of sub-models. Progress on this subject is reviewed in this report, which completes the co-ordinated research programme on 'Development of Computer Models for Fuel Element Behaviour in Water Reactors' (D-COM), initiated under the auspices of the IAEA in 1981. 73 refs, 19 figs, 4 tabs. (Atomindex citation 18:083042)

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