Recent developments in the ROCS/MC code for retrieving local power information in coarse-mesh reactor analysis
Creators
- 1. Combustion Engineering, Inc., Windsor, CT (USA). Nuclear Power Dept.
Description
The inclusion of 3-D effects in PWR analysis is necessary for accurate predictions of reactivity, power distributions, and reactivity coefficients. The ROCS/MC code system has been developed by Combustion Engineering to provide 3-D coarse mesh analysis (ROCS) with the capability to retrieve local information on flux, power and burnup (MC). A review of the finite difference representation of the MC diffusion equation, along with recent improvements to the ROCS/MC system are presented. These improvements include the implementation if fine mesh radial boundary conditions and internal calculation of coarse mesh boundary conditions, generalization of the imbedded calculation to account for the local neighboring environment, and the automation of ROCS/MC links to C-E's code system for in-core power distribution monitoring and core-follow analysis. The results of the ROCS/MC verification program are described and show good agreement with C-E's ROCS/PDQ based methodologies
Files
19045779.pdf
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Additional details
Publishing Information
- Imprint Title
- Numerical methods in nuclear engineering. Part 1
- Imprint Pagination
- 587 p.
- Journal Page Range
- p. 121-149.
- Report number
- INIS-mf--11168
Conference
- Title
- International conference on numerical methods in nuclear engineering.
- Dates
- 6-9 Sep 1983.
- Place
- Montreal, Quebec (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 19045779
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; NEUTRON FLUX; PWR TYPE REACTORS; R CODES; REACTIVITY; REACTIVITY COEFFICIENTS; SPATIAL DISTRIBUTION; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- COMPUTER CODES; DISTRIBUTION; ENRICHED URANIUM REACTORS; POWER REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS