Computer codes are widely used for NPP safety analysis within a wide set of purposes including licensing issues, safety improvement programs of existing NPPs, better utilization of nuclear fuel, higher operational flexibility, for justification of lifetime extensions, development of new emergency operating procedures, analysis of operational events, and development of accident management programmes. A safety key parameter of the evaluation and assessment of NPPs is closely related to the code ability of determining the time-space thermal-hydraulic conditions throughout the reactor coolant system and especially in the core region. At the beginning, the code development took place between the sixties and seventies where sets of conservative models are used.

Methodologies for Qualification and Application of Computational Tools for Accident Analysis in Nuclear Power Plants

Francesco D’Auria
Primo
Conceptualization
;
2006-01-01

Abstract

Computer codes are widely used for NPP safety analysis within a wide set of purposes including licensing issues, safety improvement programs of existing NPPs, better utilization of nuclear fuel, higher operational flexibility, for justification of lifetime extensions, development of new emergency operating procedures, analysis of operational events, and development of accident management programmes. A safety key parameter of the evaluation and assessment of NPPs is closely related to the code ability of determining the time-space thermal-hydraulic conditions throughout the reactor coolant system and especially in the core region. At the beginning, the code development took place between the sixties and seventies where sets of conservative models are used.
2006
Francesco, D’Auria; Anis Bousbia Salah,
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11568/907010
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