Experimental and theoretical analysis of spent AVR fuels
- 1. Forschungszentrum Juelich GmbH (Germany, F.R.)
- 2. Oesterreichisches Forschungszentrum Seibersdorf GmbH (Austria)
Description
The KFA-Juelich and the OEFZ-Seibersdorf are cooperating in a programme of experimental and theoretical analysis of spent AVR-fuel elements. The detailed experimental analysis in the OEFZ started with pebbles of 17% enriched (GLE-4) and of 93% enriched (GO) fuel showing FIMA values of about 3.5, 7.5 and 10.5% respectively. The isotopic composition of coated particles from different positions within the pebbles were measured by both gamma spectrometric and mass spectroscopic methods. To gain FIMA values from both methods Cs and Nd isotopes were included. Theoretical calculations used the new HTR-2000 programme system of KFA to perform the in-core-following of the pebbles as they move through the core. The reactor model contains 25 spectral zones and 139 regions in three dimensions in the core, fit to represent the movements of the pebbles including recycling between the inner and outer core regions. 9 refs, 21 figs, 3 tabs
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22060765.pdf
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Additional details
Publishing Information
- Imprint Title
- Uncertainties in physics calculations for gas cooled reactor cores
- Imprint Pagination
- 149 p.
- Journal Page Range
- p. 19-30.
- Report number
- IWGGCR--24
Conference
- Title
- Specialist's meeting on uncertainties in physics calculations for gas cooled reactor cores.
- Dates
- 9-11 May 1990.
- Place
- Villigen (Switzerland).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 22060765
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- AVR REACTOR; BURNUP; EXPERIMENTAL DATA; FUEL MANAGEMENT; GROUP CONSTANTS; H CODES; HIGHLY ENRICHED URANIUM; ISOTOPES; MATHEMATICAL MODELS; NUCLEAR FUELS; REACTOR FUELING; SLIGHTLY ENRICHED URANIUM; SPENT FUELS; T CODES; THEORETICAL DATA
- Descriptors DEC
- ACTINIDES; COMPUTER CODES; CROSS SECTIONS; DATA; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HOMOGENEOUS REACTORS; HTGR TYPE REACTORS; INFORMATION; ISOTOPE ENRICHED MATERIALS; MANAGEMENT; MATERIALS; METALS; NUCLEAR MATERIALS MANAGEMENT; NUMERICAL DATA; PEBBLE BED REACTORS; POWER REACTORS; REACTOR MATERIALS; REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; THORIUM REACTORS; URANIUM