Published 2013 | Version v1
Miscellaneous

Monte Carlo calculations applied to SLOWPOKE full-reactor analysis

  • 1. Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

Description

Stochastic Monte Carlo calculations are applied to the full-reactor analysis of the SLOWPOKE design. The temperature feedback of reactivity calculated by MCNP for either HEU or LEU core is in good agreement with the experimental data, with a k-eff bias of +3.3 mk for a HEU core and +6 mk for a LEU core. Two methods have been developed for core following: 1) MCNP (for transport calculation) in conjunction with WIMS (for fuel burnup advancement) and 2) SERPENT (that combines both transport and burnup capabilities), and both show very consistent results on core excess reactivity and detailed power distribution vs burnup and shim. (author)

Availability note (English)

Available as a slide presentation also.
Part of:
2nd International technical meeting on small reactors

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-12-4
Imprint Title
2nd International technical meeting on small reactors
Imprint Pagination
136 Megabytes
Journal Page Range
[4 p.]

Conference

Title
2. International technical meeting on small reactors
Dates
7-8 Nov 2012
Place
Ottawa, Ontario (Canada)

Optional Information

Notes
6 refs., 2 figs.