Published 1998 | Version v1
Book

High pressure melt ejection relevant to CANDU reactors

  • 1. Ontario Hydro Nuclear, Toronto, ON (Canada)

Description

The modelling of fuel-coolant interaction following a severe flow blockage in a single channel of a CANDU reactor is assessed. The available data that support these models is also reviewed. It is concluded that it is appropriate to employ the forced fuel-coolant interaction methodology in analyzing CANDU single channel flow blockage event with a severe power-cooling mismatch. The hydrodynamic transients are conservatively determined for various amounts of molten fuel available for discharge. The magnitude of the pressure transient and impulse loads decrease as the distance from the rupture site increases. The higher discharged mass produces more energy deposited in the bubble over the transient which results in a faster and greater pressurization of the moderator and results in higher impulsive loads on adjacent structures. (author)

Part of:
Proceedings of the Canadian Nuclear Society 19th annual conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
Imprint Title
Proceedings of the Canadian Nuclear Society 19th annual conference
Imprint Pagination
2 v.
Journal Page Range
v. 2 [15 p.]

Conference

Title
19. annual conference of the Canadian Nuclear Society
Dates
18-21 Oct 1998
Place
Toronto, Ontario (Canada)

Optional Information

Notes
10 refs., 1 tab., 12 figs.