Two-Phase Flow Heat Transfer in Nuclear Reactor Systems
1Reactor Engineering Division, Jožef Stefan Institute, Jamova 39, 1000 Ljubljana, Slovenia
2Institute of Safety Research, Helmholtz-Zentrum Dresden-Rossendorf, Bautzner Landstraße 400, 01328 Dresden, Germany
3Commissariat à l'Énergie Atomique (CEA), 17 rue des Martyrs, 38054 Grenoble, France
4Thermal-Hydraulic Safety Research Division, Korean Atomic Energy Research Institute (KAERI), Daedeok-daero 989-111, Yuseong-gu, Daejeon 305-353, Republic of Korea
5Department of Nuclear Engineering, Texas A&M University, 3133 Tamu, College Station, TX 77843-3133, USA
Two-Phase Flow Heat Transfer in Nuclear Reactor Systems
Description
Heat transfer and phase change phenomena in two-phase flows are often encountered in nuclear reactor systems and are therefore extremely important for their optimal design and safe operation. The complex phenomena observed especially during transient operation of nuclear reactor systems necessitate extensive theoretical and experimental investigations. Researchers and experts are encouraged to submit the research papers summarizing their continuing efforts to tackle various types of heat transfer phenomena in two-phase flows. The contributions dealing with phenomenological understanding, modeling, numerical simulations as well as new experiments and experimental methods are very welcome. Two-phase flow heat transfer related to safety and operation of conventional and advanced designs of nuclear reactor systems and components can be addressed. Potential topics include, but are not limited to:
- Two-phase flow and heat transfer fundamentals
- Boiling and condensation heat transfer
- CHF and post-CHF heat transfer in light water reactors
- Multiphase heat transfer in advanced reactors
- Rod-bundle thermal hydraulics
- Heat transfer phenomena during hypothetical accident conditions in nuclear systems
- Ex-vessel cooling of reactor pressure vessel
- Computational methods, modelling, new developments, validation, and application
- System thermal-hydraulic code analyses of two-phase flow heat transfer
- CFD analyses or multiscale analyses of two-phase flow heat transfer
- Experiments and analysis of two-phase flow with heat transfer
- Advanced instrumentation and measurement techniques
Before submission authors should carefully read over the journal's Author Guidelines, which are located at http://www.hindawi.com/journals/stni/guidelines/. Prospective authors should submit an electronic copy of their complete manuscript through the journal Manuscript Tracking System at http://mts.hindawi.com/ according to the following timetable: