Effect of burnup on ACR-700 3-D reactivity devices cross sections
- Institut de Genie Nucleaire, Ecole Polytechnique de Montreal, 2900 Boulevard Edouard-Montpetit, Montreal, Que. H3T 1J4 (Canada)
Full core analysis of typical power reactors being generally performed using few groups diffusion theory, it is necessary to generate beforehand, using a lattice code, the required few group cross sections and diffusion coefficients associated with each region in the core. For CANDU-type reactors including the Advanced CANDU Reactor (ACR), the problem is more complex because these reactors contain vertical reactivity devices that are located between two horizontal fuel bundles. The usual calculation scheme relies in this case on a 2-D fuel cell calculation to generate the few group fuel properties and on a 3-D supercell calculation for the analysis of the reactivity devices present in the core. Because of its complexity, the supercell calculations are generally performed using simplified fuel geometries. In this paper, the different stages involved in the reactor physics simulations for ACR will be explained focusing particularly on a study of the burnup dependence of the incremental cross section associated with zone control units (ZCU). The use of these incremental cross sections for finite core calculations will also be presented. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 22039494
- Resource Relation:
- Conference: PHYSOR-2006: American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, Vancouver, BC (Canada), 10-14 Sep 2006; Other Information: Country of input: France; 15 refs.
- Country of Publication:
- United States
- Language:
- English
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