Published 1994 | Version v1
Miscellaneous

Simulation of the transport of fission products in the fuel-to-sheath gap of defective CANDU fuel rods

Description

The differential equations describing the transport of volatile fission products within the fuel to sheath gap in a CANDU fuel element have been established, and solved both analytically and numerically, for the two different cases: normal operation and reactor accident conditions. For both cases, the results obtained were in very good agreement, and well within the uncertainty of some of the parameters, such as the diffusion coefficients. The computer code PRODFISS has been written in a general way so that the model can be applied to other volatile fission products and to LWR fuel elements. 11 refs., 1 tab., 6 figs

Part of:
Proceedings of the 1994 nuclear simulation symposium

Additional details

Publishing Information

Imprint Title
Proceedings of the 1994 nuclear simulation symposium
Imprint Pagination
290 p.
Journal Page Range
p. 230-243.
Report number
INIS-mf--14840

Conference

Title
1994 nuclear simulation symposium.
Dates
12-14 Oct 1994.
Place
Pembroke, ON (Canada).

Optional Information