Published 2010
| Version v1
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Uncertainty and similarity analysis between simplified models of CANDU-6 and TCR reactors using TSUNAMI
Description
The TSUNAMI code, a component of the SCALE package was employed to perform a sensitivity and uncertainty (S/U) analysis of simplified full-core models of a CANDU-6 reactor (CANada Deuterium Uranium, henceforth referred to as C6) and a proposed Thorium based CANDU Reactor (TCR). The code utilizes an adjoint-based first-order linear perturbation theory to generate sensitivity coefficients for the k-effective value(k) and other reactivity coefficients with respect to nuclear data. The coupling of these sensitivity data with the underlying nuclear covariance data yields uncertainties in keff or reactivity coefficients due to uncertainties in the nuclear data.
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Additional details
Publishing Information
- Imprint Pagination
- 4 p.
- Report number
- AECL-CW--123740-CONF-003
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 49041755
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; NATURAL URANIUM; REACTIVITY COEFFICIENTS; THORIUM
- Descriptors DEC
- ACTINIDES; ELEMENTS; HEAVY WATER MODERATED REACTORS; METALS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; URANIUM
Optional Information
- Notes
- 4 refs., 4 tabs., 1 fig.