Actions for Prediction of thermal-hydraulic performance of gas-cooled fast breeder reactors. Final report

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Prediction of thermal-hydraulic performance of gas-cooled fast breeder reactors. Final report

Author
Gazley, C. Jr.
Published
United States : [publisher not identified], 1977.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1977.
Physical Description
microfiche : negative ; 11 x 15 cm
Additional Creators
Catton, J., Grzesik, J., Harpole, G. H., Krase, W. H., Matyskiela, W., and Yao, L. S.

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Summary
The report describes work performed under a project to examine the thermal-hydraulic performance of gas-cooled fast breeder reactors (GCFRs). Existing GCFR designs are briefly described with emphasis on the core cooling and associated systems. Factors affecting the convective heat transfer and pressure drop in the core are examined, particularly the effects of surface roughness on the enhancement of heat transfer, the effects of the variation of the coolant's thermophysical properties with temperature and composition, and the influence of cross flow and cross mixing. The characteristics of other components of the cooling system, the helium circulator, and the steam generator are examined with particular emphasis on off-normal operation. Existing computer codes for the prediction of both normal and abnormal operations are described and compared. Two new codes, developed under this project, are described, and some preliminary results are given of their application to GCFR thermal-hydraulic performance. These codes are AVFLO, a relatively simple and inexpensive program for the evaluation of reactor core axial temperature distribution at steady-state conditions, and RETSAC which is of the SABRE/COBRA IV category but appears to enable detailed analysis of reactor transients with little or no iteration. Problem areas pertinent to cooling-system performance and safety are summarized, and recommendations are made for additional research in areas that need attention in order to assure economical design and safe operation.
Report Numbers
EPRI-NP-156
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
OSTI Identifier 7216058
Research organization: RAND Corp., Santa Monica, CA (United States).
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