Benchmark Consolidated Results Against Experimental Data from ATI-1. Annex IV
Creators
Description
The ATI-1 benchmark analysis, including the reactor specification and experimental data, is documented. It consists of a fuelled experiment conducted at the TRIGA (Training, Research, Isotopes, General Atomics) MARK II reactor of the Atominstitut (ATI) at Technische Universität (TU) Wien. Experimental data were obtained through the analysis by axial gamma ray spectrometry of several irradiated fuel elements (FEs) of known operating history. The measurement purpose was to provide information about fuel composition (e.g. production and depletion of major and minor actinides and fission products) under different irradiation conditions. Additional input data, such as ATI TRIGA reactor core geometry and configuration, in core neutron flux spectra and distributions, reactor operating history are also provided. Two participants (from Austria and Thailand) contributed at the ATI-1 benchmark using Monte Carlo computer codes to model the experiment and calculate data to be compared against experimental values for each scanned fuel element.
Additional details
Identifiers
Publishing Information
- ISBN
- 978-92-0-101222-7
- Imprint Title
- Benchmarks of Fuel Burnup and Material Activation Computational Tools Against Experimental Data for Research Reactors. Results of a Coordinated Research Project
- Imprint Pagination
- 278 p.
- Journal Page Range
- p. 107-125
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1992
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 53082613
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- ACTINIDES; BENCHMARKS; COMPUTER CODES; COMPUTERIZED SIMULATION; FISSION PRODUCTS; GAMMA SPECTROSCOPY; GEOMETRY; IRRADIATION; MONTE CARLO METHOD; NEUTRON FLUX; REACTOR CORES; SPECIFICATIONS; SPECTRA; SPENT FUEL ELEMENTS; SPENT FUELS; TRIGA TYPE REACTORS
- Descriptors DEC
- CALCULATION METHODS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; ISOTOPES; MATERIALS; MATHEMATICS; METALS; NUCLEAR FUELS; RADIATION FLUX; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; SOLID HOMOGENEOUS REACTORS; SPECTROSCOPY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs., 11 figs., 11 tabs.