Published August 1983
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Comparison of some measurements in the Greek Research Reactor-1 (GRR-1) with 20% and 93% enriched uranium fuel elements
- 1. Reactor Department, N.R.C. 'Democritos', Athens (Greece)
Description
Experimental results of the core performance of the GRR-1 with 20% and 93% enriched 235U are compared. In particular, the rod worth, the flux distribution (axial and radial), the temperature, and the void effects are analyzed and compared for the two cores. The experimental results are in good agreement with benchmark calculations for this reactor and for other similar reactors. Although the fuel elements of the two cores do not have the same number of plates, the results are of special significance, since they present the only experimental comparative work known so far on the core conversion problem from the use of highly enriched uranium to the use of low enriched uranium fuels. (author)
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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. 644-651
- 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
- 36026381
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CONTROL ROD WORTHS; DEMOCRITUS REACTOR; EXPERIMENTAL DATA; HIGHLY ENRICHED URANIUM; MODERATELY ENRICHED URANIUM; NEUTRON FLUX; SPATIAL DISTRIBUTION; TEMPERATURE COEFFICIENT; VOID COEFFICIENT
- Descriptors DEC
- ACTINIDES; DATA; DISTRIBUTION; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; EVALUATION; INFORMATION; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NUMERICAL DATA; POOL TYPE REACTORS; RADIATION FLUX; REACTIVITY COEFFICIENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs, 4 figs, 2 tabs
- Secondary number(s)
- CONF--801144; INIS-XA-C--021