Uncertainty and Sensitivity Studies with TRACE-SUSA and TRACE-DAKOTA by Means of Transient BFBT Data
Creators
- 1. Karlsruhe Institute of Technology, Institute for Neutron Physics and Reactor Technology, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany
- 2. Departamento de Sistemas Energeticos ETSI Minas, Universidad Politecnica de Madrid, Alenza 4, 28003 Madrid, Spain
Description
In the present paper, an uncertainty and sensitivity study is performed for transient void fraction and pressure drop measurements. Two transients have been selected from the NUPEC BFBT database. The first one is a turbine trip without bypass and the second one is a trip of a recirculation pump. TRACE (version 5.0 patch 2) is used for the thermohydraulic study and SUSA and DAKOTA are used for the quantification of the model uncertainties and the evaluation of the sensitivities. As uncertain parameters geometrical values, hydraulic diameter, and wall roughness are considered while mass flow rate, power, pressure, and inlet subcooling (inlet temperature) are chosen as boundary and input conditions. Since these parameters change with time, it is expected that the importance of them on pressure drop and void fraction will change, too. The results show that the pressure drop is mostly sensitive to geometrical variations like the hydraulic diameter and the form loss coefficient of the spacer grid. For low void fractions, the parameter of the highest importance is the inlet temperature/subcooling while at higher void fraction the power is also of importance.
Files
10.1155_2013_565246.pdf
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Additional details
Identifiers
- DOI
- 10.1155/2013/565246;
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations
- Journal Volume
- 2013
- Journal Page Range
- 1-9
- ISSN
- 1687-6075
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BOUNDARY CONDITIONS; EVALUATION; FLOW RATE; HYDRAULIC TURBINES; HYDRAULICS; MASS TRANSFER; PRESSURE DROP; PRESSURE MEASUREMENT; PUMPS; ROUGHNESS; SENSITIVITY ANALYSIS; SUBCOOLING; THERMAL HYDRAULICS; TRANSIENTS; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- COOLING; EQUIPMENT; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MACHINERY; MECHANICS; SURFACE PROPERTIES; TURBINES; TURBOMACHINERY
Optional Information
- Copyright
- © Author(s)
- Notes
- Record automatically processed
- Funding organization
- Nuclear Safety Research