The key issues in transient analysis calculations which affect the radiological consequences following design-basis steam generator tube rupture accidentsFunded under: FP3-NFS 1
This report assesses the transient response of the reactor coolant system (RCS) to a steam generator tube rupture (SGTR) fault and, in a number of sensitivity studies, identifies the transient analysis parameters to which the radiological consequences of a SGTR fault are sensitive. The key parameter which determines the ability of fission products to be maintained in the secondary coolant in a sequence involving a SGTR with a stuck open secondary relief valve has been shown, in an earlier study initiated by the reactor safety working group (RSWG), to be the maintenance of recirculating conditions in the steam generator downcomer. This report identifies the key parameters which affect the ability to maintain recirculation following a SGTR with a stuck open secondary relief valve. In a number of cases, recirculation is calculated to be lost for short period, of the order of one minute. If experimental evidence can be provided to support claims of retention during these periods, then the calculated release for these sequences could be substantially reduced.
Bibliographic Reference: EUR 16244 EN (1996) 118pp., FS, ECU 11.50
Availability: Available from the (2)
ISBN: ISBN 92-827-8282-4
Record Number: 199611432 / Last updated on: 1996-12-16
Original language: en
Available languages: en