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• Flow and rupture study of liquid film on corrugated plate wall are reviewed. • Chaotic analysis of film thickness series will be a prospect research direction. • Film rupture mechanism cannot be explained by surface wave disturbance model. • More study will be focused on rupture phenomenon at the corrugated plate corner. Steam generated by steam generator in a nuclear power plant must firstly be subjected to steam-water separation treatment before entering the turbine. The research on flow and rupture characteristics of the liquid film on the wall surface of corrugated plate has important and practical significance for improving the separation efficiency. Since the 1940s, researchers from the United States, France, Japan and other countries have carried out related researches. With the rapid development of steam-water separation technology, many scholars have carried out a large number of experiments, theoretical study and numerical calculations on this phenomenon. Based on the published papers, the research progress and significant achievements of the flow and rupture characteristics of the liquid film on corrugated plate wall are reviewed. Shortcomings of past research and prospects for future research are summarized and proposed, respectively, which provides a reference for improvement of separation efficiency of the corrugated plate dryer. [ABSTRACT FROM AUTHOR]

Abstract: The joint paper presents a common view of fast reactor specific missions in the development of nuclear energy and a cross-analysis of merits and demerits of several Fast Reactors concepts studied worldwide and especially in the Generation-IV International Forum (GIF) framework. The paper provides the context for fast reactors development in the United States, France and Japan and focuses on the comparison on Sodium-cooled Fast Reactor (SFR), Gas-cooled Fast Reactor (GFR), and Lead-cooled Fast Reactor (LFR), i.e. the three fast reactor concepts that have the potential to meet the nuclear fuel cycle sustainability goals. The information provided in the article permits the reader to understand each country''s objectives to see that not only the objectives searched for but also the technical orientations are converging. The authors underline that SFR technology evaluation relies significantly on the substantial base technology development programs within each country which is without comparison for the other two fast reactor technologies, e.g., SFR technology has already been developed to commercial or near commercial scale in each country whereas the performance of LFR and GFR technology is still uncertain. The main GFR merits are the potential for high temperatures and the easier possibilities for inspections and repairs. The main challenges are the fuel (fabrication, in-pile behavior), materials for high temperatures, and the implementation of mitigation means to manage severe core degradation. The main LFR merit is the lack of chemical reactivity of the lead coolant with air and water. The main challenges are the development of corrosion resistant structural and cladding materials, the implementation of mitigation means to manage severe core degradation, the density of the lead, and the comparably large core size. The selection of a reference fast reactor concept in view of possible industrialization is made on a national base, taking into account the each countries’ strategic objectives, existing technology base, the proven or expected technical performance, the R&D challenges and technical means to conduct that R&D, the possibility to share development costs and risks, etc. It is important to note that in different contexts, the U.S., French, and Japanese organizations have selected the SFR as their reference fast reactor concept. [Copyright &y& Elsevier]