Impact of system parameters on quenching heat transfer in the candidate materials for accident tolerant fuel-cladding in LWRs
Creators
- 1. Division of Advanced Nuclear Engineering, POSTECH, Pohang 790-784 (Korea, Republic of)
- 2. Thermal hydraulic and severe accident safety research division, KAERI, Daejeon 34057 (Korea, Republic of)
- 3. Department of Engineering Physics, University of Wisconsin-Madison, Madison, WI 53706 (United States)
Description
Highlights: • Quenching heat transfer was evaluated by the experimental and system code for the ATF application. • Thermo-physical properties of cladding and system parameters all impact the quenching. • Thermo-physical properties of cladding have little impact of the quenching compared to the system parameters. - Abstract: We investigated a potential impact of the candidate materials (FeCrAl, SiC-CVD, and Zry-4) for the Accident Tolerant Fuel-cladding (ATF) in the quenching heat transfer according to the system parameters such as liquid subcooling, pressure, and flooding rates. Results obtained by water quenching experiment and system code analysis using MARS 3D-VESSEL are presented that the quenching heat transfer including the post-CHF parameters (i.e., minimum film-boiling temperature) is more influenced by the system parameters compared to change of the cladding materials. Current models of minimum film-boiling temperature in system code are also discussed for the application of ATF and its oxidation. Select option in the model library is proposed to consider the surface parameters using weighting term in thermal-hydraulic system code.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2019.01.015Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2019.01.015;
- PII
- S0306454919300209;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 129
- Journal Page Range
- p. 375-389
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51008032
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; BOILING POINTS; CHEMICAL VAPOR DEPOSITION; CLADDING; FILM BOILING; FUEL-CLADDING INTERACTIONS; HEAT TRANSFER; QUENCHING; SILICON CARBIDES; SUBCOOLING; THERMAL HYDRAULICS; WATER; WATER COOLED REACTORS; ZIRCALOY 4
- Descriptors DEC
- ALLOYS; ALLOY-ZR98SN-4; BOILING; CARBIDES; CARBON COMPOUNDS; CHEMICAL COATING; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; COOLING; CORROSION RESISTANT ALLOYS; DEPOSITION; ENERGY SOURCES; ENERGY TRANSFER; FLUID MECHANICS; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HYDRAULICS; HYDROGEN COMPOUNDS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MECHANICS; NUCLEAR FUELS; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; REACTOR MATERIALS; REACTORS; SILICON COMPOUNDS; SURFACE COATING; THERMODYNAMIC PROPERTIES; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION TEMPERATURE; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- © 2019 Published by Elsevier Ltd.