Abstract
High temperature reactors (HTR) are being considered for deployment around the world because of their excellent safety features. The fuel is embedded in a graphite moderator and can sustain very high temperatures. However, the appearance of hot spots in the pebble bed cores of HTR's may affect the integrity of the pebbles. A good prediction of the flow and heat transport in such a pebble bed core is a challenge for available turbulence models and such models need to be validated. In the present article, quasi direct numerical simulations (q-DNS) of a pebble bed configuration are reported, which may serve as a reference for the validation of different turbulence modeling approaches. Such approaches can be used in order to perform calculations for a randomly arranged pebble bed. Simulations are performed at a Reynolds number of 3088, based on pebble diameter, with a porosity level of 0.42. Detailed flow analyses have shown complex physics flow behavior and make this case challenging for turbulence model validation. Hence, a wide range of qualitative and quantitative data for velocity and temperature field have been extracted for this benchmark. In the present article (part I), results related to the flow field (mean, RMS and covariance of velocity) are documented and discussed in detail. Moreover, the discussion regarding the temperature field will be published in a separate article.
| Original language | English |
|---|---|
| Pages (from-to) | 473-489 |
| Number of pages | 17 |
| Journal | Nuclear Engineering and Design |
| Volume | 263 |
| DOIs | |
| State | Published - 2013 |
| Externally published | Yes |
Bibliographical note
Funding Information:The work described in this paper is funded by the Dutch Ministry of Economic Affairs and the FP7 EC Collaborative Project THINS No. 249337. The authors are grateful for the valuable comments and suggestions given by Andreas Class (KIT), Yassin A. Hassan (Texas A&M), Iztok Tiselj (JSI), Danny Lathouwers and Dimitrios Pavlidis (TUD) during the execution of the THINS project.
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- General Materials Science
- Nuclear Energy and Engineering
- Safety, Risk, Reliability and Quality
- Waste Management and Disposal
- Mechanical Engineering
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