Steady and unsteady calculations on thermal striping phenomena in triple-parallel jet
- 1. Nuclear Engineering Division, Argonne National Laboratory, Lemont, IL 60439 (United States)
- 2. Mathematics and Computer Science Division, Argonne National Laboratory, Lemont, IL 60439 (United States)
- 3. Computing, Environment and Life Sciences Directorate, Argonne National Laboratory, Lemont, IL 60439 (United States)
Description
Highlights: • Both steady (RANS) and unsteady (URANS, LES) methods were applied to study thermal striping. • The unsteady results exhibited reasonably good agreement with experimental results. • The parametric studies on the effects of mesh density and boundary conditions on the accuracy of the overall solutions were also conducted. - Abstract: The phenomenon of thermal striping is encountered in liquid metal cooled fast reactors (LMFR), in which temperature fluctuation due to convective mixing between hot and cold fluids can lead to a possibility of crack initiation and propagation in the structure due to high cycle thermal fatigue. Using sodium experiments of parallel triple jets configuration performed by Japan Atomic Energy Agency (JAEA) as benchmark, numerical simulations were carried out to evaluate the temperature fluctuation characteristics in fluid and the transfer characteristics of temperature fluctuation from fluid to structure, which is important to assess the potential thermal fatigue damage. In this study, both steady (RANS) and unsteady (URANS, LES) methods were applied to predict the temperature fluctuations of thermal striping. The parametric studies on the effects of mesh density and boundary conditions on the accuracy of the overall solutions were also conducted. The velocity, temperature and temperature fluctuation intensity distribution were compared with the experimental data. As expected, steady calculation has limited success in predicting the thermal–hydraulic characteristics of the thermal striping, highlighting the limitations of the RANS approach in unsteady heat transfer simulations. The unsteady results exhibited reasonably good agreement with experimental results for temperature fluctuation intensity, as well as the average temperature and velocity components at the measurement locations.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2016.06.015Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2016.06.015;
- PII
- S0029-5493(16)30174-1;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 312
- Journal Page Range
- p. 429-437
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 16. International Topical Meeting on Nuclear Reactor Thermal Hydraulics
- Acronym
- NURETH-16
- Dates
- 30 Aug - 4 Sep 2015
- Place
- Chicago, IL (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48062550
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ACCURACY; BENCHMARKS; BOUNDARY CONDITIONS; COMPUTERIZED SIMULATION; CRACK PROPAGATION; DAMAGE; EXPERIMENTAL DATA; HEAT TRANSFER; JAEA; JETS; LMFBR TYPE REACTORS; NAVIER-STOKES EQUATIONS; PARAMETRIC ANALYSIS; SODIUM; TEMPERATURE DEPENDENCE; THERMAL FATIGUE; THERMAL HYDRAULICS
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; DATA; DIFFERENTIAL EQUATIONS; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; EQUATIONS; FAST REACTORS; FATIGUE; FBR TYPE REACTORS; FLUID MECHANICS; HYDRAULICS; INFORMATION; JAPANESE ORGANIZATIONS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; MECHANICS; METALS; NATIONAL ORGANIZATIONS; NUMERICAL DATA; PARTIAL DIFFERENTIAL EQUATIONS; REACTORS; SIMULATION
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.