Thermal-hydraulic Experiments Supporting the MYRRHA Fuel Assembly
- 1. Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (Germany)
- 2. Belgian Nuclear Research Center (SCK-CEN), Mol (Belgium)
Description
The development of the LBE-cooled MYRRHA fuel assemblies is supported by an extensive thermal-hydraulic experimental program, as well as numerical studies. For the safety assessment of the reactor, several experimental campaigns considering fuel assembly mockups in representative operating conditions have been completed, and others are ongoing and planned at KIT (Germany) and SCK•CEN (Belgium). These are individually focused on specific issues, such as the heat transfer and pressure drop in nominal conditions, effects of local blockages and their formation, and influences of inter-wrapper flow between neighboring fuel assemblies. Heated tests using LBE, as well as isothermal studies with water as a model fluid, are considered. This article summarizes the main results of completed projects, highlighting the accuracy of existing correlations, and the relevance of hot spots based on local temperature distribution both at the wall and in the fluid. Moreover, the status of ongoing work is presented and the main open thermal-hydraulic issues for supporting the development of the MYRRHA fuel assembly are identified. (author)
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Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Programme and Papers
- Imprint Pagination
- vp.
- Journal Page Range
- 10 p.
- Report number
- IAEA-CN--245
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49085982
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; BELGIUM; EXPERIMENT PLANNING; FEDERAL REPUBLIC OF GERMANY; FLOW MODELS; FUEL ASSEMBLIES; HEAT TRANSFER; HOT SPOTS; MOCKUP; MYRRHA FACILITY; NUMERICAL ANALYSIS; PRESSURE DROP; RISK ASSESSMENT; SAFETY ANALYSIS; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS
- Descriptors DEC
- ACCELERATOR-DRIVEN SUBCRITICAL SYSTEMS; DEVELOPED COUNTRIES; ENERGY TRANSFER; EPITHERMAL REACTORS; EUROPE; EXPERIMENTAL REACTORS; FAST REACTORS; FLUID MECHANICS; HYDRAULICS; LEAD COOLED REACTORS; LEAD-BISMUTH COOLED REACTORS; LIQUID METAL COOLED REACTORS; MATHEMATICAL MODELS; MATHEMATICS; MECHANICS; PLANNING; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STRUCTURAL MODELS; SUBCRITICAL ASSEMBLIES; WESTERN EUROPE
Optional Information
- Notes
- 17 refs., 7 figs., 1 tab.
- Secondary number(s)
- IAEA-CN--245-283