Supercritical Water-Cooled Reactors
1Sino–French Institute of Nuclear Engineering and Technology, Sun Yat–sen University, Zhuhai, Guangdong 519082, China and School of Physics and Engineering, Haizhu, Guangzhou, Guangdong 510275, China
2INSTN/PSNE, The French Alternative Energies and Atomic Energy Commission (CEA) Saclay, 91191 Gif–sur–Yvette, France
3School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shaanxi 710049, China
Supercritical Water-Cooled Reactors
Description
Supercritical water–cooled reactor (SCWR) is the water–cooled reactor using supercritical pressure water as a coolant. It is considered as one of the most promising Generation IV reactors, due to its advantages of plant simplification and high thermal efficiency.
We invite investigators to contribute original research articles as well as review articles that will stimulate the continuing research and development of SCWR core design, fuel design, materials, chemistry, corrosion, thermal hydraulics, safety analysis, and so on. Potential topics include, but are not limited to:
- Reactor core and fuel designs
- Materials, chemistry, and corrosion
- Thermal hydraulics and safety analysis
- Plant systems, structures, and components
- Computational fluid dynamics (CFD) and coupled codes
- Neutronic properties
- Balance of plant
- Other applications
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/submit/journals/stni/swr/ according to the following timetable:
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