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Comparison of calculated quantities with measured quantities for the LEU-fueled Ford Nuclear Reactor
Bretscher, M.M.; Snelgrove, J.L.
Argonne National Lab., IL (USA)1982
Argonne National Lab., IL (USA)1982
AbstractAbstract
[en] The Ford Nuclear Reactor (FNR) went critical on December 8, 1981 with 23 LEU fuel elements. Five of these 23 elements were fabricated by CERCA and the others by NUKEM. Since that time a substantial data base of experimental results for LEU cores has been accumulated by the University of Michigan FNR staff. This paper compares some of the experimental data with analytical calculations based, for the most part, on three-dimensional diffusion theory. The critical configuration, control rod worths, axial rhodium reaction rate profiles and thermal flux distributions have been calculated and compared with measurements
Primary Subject
Source
1982; 30 p; International meeting on research and test reactor core conversions from HEU to LEU fuels; Argonne, IL (USA); 8 - 10 Nov 1982; Available from NTIS, PC A03/MF A01 as DE83007725
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ENRICHED URANIUM REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, KINETICS, POOL TYPE REACTORS, RADIATION FLUX, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TEST REACTORS, THERMAL REACTORS, TRAINING REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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