Published 1995
| Version v1
Miscellaneous
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Application of the feedback model for the history base using DRAGON
Creators
- 1. Ecole Polytechnique, Montreal, PQ (Canada). Inst. de Genie Nucleaire
Description
We present here a new model for cross sections parametrization. This model allows us to generate a coherent set of the nuclear cross sections for a CANDU cell as a function of the concentration of the various isotopes in the core, moderator and coolant density and temperatures (fuel, coolant and moderator). Simple physical considerations lead us to determine the law of variations of the mean cross sections as functions of these parameters. They permit the computation of the cross sections for each state of the reactor core, using a unique library for each type of cell and containing the nuclear cross sections computed at rated (nominal) conditions and feedback coefficients. (author). 3 refs
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29000311.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the 19. Canadian Nuclear Society simulation symposium
- Imprint Pagination
- [350 p.].
- Journal Page Range
- [12 p.].
- Report number
- INIS-CA--0010
Conference
- Title
- 19. CNS simulation symposium.
- Dates
- 16-17 Oct 1995.
- Place
- Hamilton, ON (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 29000311
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; CROSS SECTIONS; D CODES; GROUP CONSTANTS; LATTICE PARAMETERS; MULTIGROUP THEORY; NEUTRON TRANSPORT THEORY; REACTOR CORES
- Descriptors DEC
- COMPUTER CODES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; TRANSPORT THEORY