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- W137140934 abstract "To understand the reactor physics in enriched-fuel, graphite-moderated thermal reactors theoretical and experimental investigations were performed. A critical assembly was used to obtain the creticality data. An approach of criticality calculations was developed, and it is demonstrated that the procedure is feasible in the limited area such as in the case of enriched-fuel, graphite-moderated small thermal reactors. The agreement between the theoretical and experimental criticality data is good. The effect of chemical bending in the graphite is of interest in the thermal reactor. Results of theoretical calculations are also presented. (auth)" @default.
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- W137140934 date "1962-06-15" @default.
- W137140934 modified "2023-09-27" @default.
- W137140934 title "MEASUREMENTS AND CALCULATIONS FOR GRAPHITE-MODERATED ENRICHED-FUEL CRITICAL ASSEMBLY, SHE" @default.
- W137140934 hasPublicationYear "1962" @default.
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