Modelling of the HFR-EU1bis Experiment and Thermomechanical Evaluation
- 1. NRG, Nuclear Research and consultancy Group, P.O. Box 25, NL-1755 ZG Petten (Netherlands)
Description
The article describes how numerical modelling has been successfully applied during the design and evaluation of the HFREU1bis HTR fuel pebble irradiation experiment conducted by the Joint Research Centre Institute for Energy (JRC) in the HFR Petten, The Netherlands [1]. HFR-EU1bis contains 5 HTR fuel pebbles that are placed in a graphite shroud. This assembly is placed in a containment tube, which is again placed in another containment, which is in contact with the HFR cooling water. The experimental requirement is to maintain a central temperature of 1250°C for all pebbles throughout the irradiation time of 250 efpd. This was achieved by tailoring the gas gaps in the sample holder such that the axial heat generation profile is compensated. Determining the dimensions of the components of the experiment has been done using a thermomechanical finite element model. A combination of numerical and analytical techniques has been applied to minimise calculation times, which will be explained in the article. The thermomechanical finite element model includes the thermal influence of changing gas gap dimensions due to expansion. Heat transfer by radiation through the gap gas has been modelled as well. Results of the model have been compared with measured temperatures. After some adjustments of the model parameters, which will be explained in the article, good agreement has been found between calculated and measured temperatures. Additionally, the influence of irradiation on graphite thermal conductivity and thermal expansion has been included in the model. Due to irradiation damage the thermal conductivity of graphite decreases and thermal expansion generally increases, leading to increasing thermal stresses. Due to burn up however, the heat flux decreases during irradiation, which leads to a decrease in thermal stresses. To evaluate the influence of these competing mechanisms, the thermal stress evolution during irradiation has been calculated and will be discussed. (author)
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Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- INIS-ZA--23M0145
Conference
- Title
- 3. International Topical Meeting on High Temperature Reactor Technology
- Dates
- 1-5 Oct 2006
- Place
- Johannesburg (South Africa)
INIS
- Country of Publication
- South Africa
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54089474
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; COMPARATIVE EVALUATIONS; CONTAINMENT; COOLING; DESIGN; FEDERAL REPUBLIC OF GERMANY; FINITE ELEMENT METHOD; FORSCHUNGSZENTRUM JUELICH; GRAPHITE; HEAT; HEAT TRANSFER; HTGR TYPE REACTORS; IRRADIATION; NUCLEAR FUELS; SIMULATION; WATER
- Descriptors DEC
- CALCULATION METHODS; CARBON; DEVELOPED COUNTRIES; ELEMENTS; ENERGY; ENERGY SOURCES; ENERGY TRANSFER; EUROPE; EVALUATION; FUELS; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; HYDROGEN COMPOUNDS; MATERIALS; MATHEMATICAL SOLUTIONS; MINERALS; NATIONAL ORGANIZATIONS; NONMETALS; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; REACTOR MATERIALS; REACTORS; WESTERN EUROPE
Optional Information
- Notes
- Document from Juelich Preservation Project; 7 refs., 8 figs.