Core physics analysis in support of the FNR HEU-LEU demonstration experiment
- 1. Department of Nuclear Engineering, University of Michigan (United States)
Description
A core neutronics analysis has been undertaken to assess the impact of low-enrichment fuel on the performance and utilization of the FNR As part of this analytic effort a computer code system has been assembled which will be of general use in analyzing research reactors with MTR-type fuel. The code system has been extensively tested and verified in calculations for the present high enrichment core. The analysis presented here compares the high-and-low enrichment fuels in batch and equilibrium core configurations which model the actual FNR operating conditions. The two fuels are compared for cycle length, fuel burnup, and flux and power distributions, as well as for the reactivity effects which are important in assessing the impact of LEU fuel on reactor shutdown margin. (author)
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36023739.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology
- Imprint Pagination
- 671 p.
- Journal Page Range
- p. 450-498
- Report number
- ANL/RERTR/TM--3
Conference
- Title
- International meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR)
- Dates
- 12-14 Nov 1980
- Place
- Argonne, IL (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36023739
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; COMPUTER CALCULATIONS; FNR REACTOR; FUEL CYCLE; HIGHLY ENRICHED URANIUM; NEUTRON FLUX; POWER DISTRIBUTION; REACTOR CORES; REACTOR LATTICE PARAMETERS; REACTOR SAFETY; SLIGHTLY ENRICHED URANIUM
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; MATERIALS; METALS; POOL TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; TRAINING REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 20 refs, 13 figs, 10 tabs
- Secondary number(s)
- CONF--801144; INIS-XA-C--021