Published August 1983 | Version v1
Miscellaneous Open

Recent developments in the ROCS/MC code for retrieving local power information in coarse-mesh reactor analysis

  • 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

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Part of:
Numerical methods in nuclear engineering. Part 1

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).

Optional Information