M. Staat, PROBABILISTIC ASSESSMENT OF THE FRACTURE-MECHANICS BEHAVIOR OF AN HTR-MODULE PRIMARY CIRCUIT PRESSURE BOUNDARY, Nuclear Engineering and Design, 160(1-2), 1996, pp. 221-236
In this paper the fracture mechanical behaviour of the primary circuit
pressure boundary of a planned HTR-module reactor for electricity and
steam generation under normal operation is assessed probabilistically
. First and second order reliability methods (FORM-SORM) are used to c
alculate failure probabilities. They also allow a simplified analysis
of the leak-before-break (LBB) behaviour. No LBB was probabilistically
identified for the reactor pressure vessel. However, failure of the p
ressure vessel unit in normal operation probably originates from the c
onnecting pressure vessel or the steam generator pressure vessel. They
show LBB in probabilistic terms.