Published May 2017 | Version v1
Journal article

MAAP 5.04 ex-vessel CRD tube heat transfer and melting model

Description

Highlights: • Enhancements are made to consider ex-vessel CRD housing heat transfer and melting. • The BWR Station Blackout (SBO) scenario was simulated using the new code. • The ex-vessel CRD tube heat transfer did not affect the time of vessel failure. - Abstract: Enhancements are made in the Boiling Water Reactor (BWR) version of MAAP 5.04 to consider ex-vessel Control Rod Drive (CRD) housing heat transfer and melting. The in-vessel CRD tube model is extended below the reactor vessel and conduction and radiative heat transfer between the lower head, CRD tubes, pedestal gas and pedestal wall are considered. The possibility of corium melt flowing into collapsed CRD tubes and causing creep rupture of CRD tubes outside the reactor vessel, leading to vessel failure, is considered. Lastly, ex-vessel CRD tube melting due to the corium jet exiting the breached reactor vessel after vessel failure is considered. The BWR Station Blackout (SBO) scenario was simulated using the new code. The results show that explicitly modeling the ex-vessel CRD tube heat transfer did not affect the time of vessel failure. Also, vessel failure due to corium ingress into ex-vessel CRD tubes was not predicted. A small, but nontrivial mass of steel from ablated ex-vessel CRD tubes was added to the debris bed on the pedestal floor after vessel failure.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2017.01.028

Additional details

Identifiers

DOI
10.1016/j.anucene.2017.01.028;
PII
S0306-4549(16)30541-2;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
103
Journal Page Range
p. 265-274
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Copyright
Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.