A Model for the Transient Release of Fission Products from UO2Fuel: Gasout Code Description

Author:

Tayal Mukesh1,Macdonald Lorne D.1,Kohn Erl1,Dovigo Walter P.1

Affiliation:

1. Atomic Energy of Canada Limited Sheridan Park Research Community, Mississauga, Ontario, Canada L4K 1B2

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference16 articles.

1. I. J. HASTINGS, “Structures in Irradiated UO2Fuel from Canadian Reactors,” AECL-MISC-249, Atomic Energy of Canada Limited (1983).

2. A microstructure-dependent model for fission product gas release and swelling in UO2 fuel

3. M. TAYAL, “Modelling CANDU Fuel Under Normal Operating Conditions: ELESTRES Code Description,” AECL-9331, Atomic Energy of Canada Limited (1987).

4. A. H. BOOTH, “A Method of Calculating Fission from UO2Fuel and Its Application to the X-2-f Loop Test,” AECL-496, Atomic Energy of Canada Limited (Sep. 1957).

5. A. H. BOOTH and G. T. RYMER, “Determination of the Diffusion Constant of Fission Xe in UO2Crystals and Sintered Compacts,” AECL-692, Atomic Energy of Canada Limited (Aug. 1959).

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