In this paper the authors review 25 original Small and Medium sized Reactor designs currently under development, licensing procedure or in operation. Technology overview, safety features and ability to mitigate proliferation are considered. In order to show common research trends and highlight the features of particular designs the authors choose to classify the reactors according to used technology and cooling medium. The main requirement for a new reactor design is to secure inherent and passive safety features, thus different ways to achieve it are shown. The Pressurized Water Reactor (PWR) is the most advanced and most commonly used technology. In PWR, passiveness and inherency of safety features are ensured by integrating steam generators inside the Reactor Pressure Vessel (RPV). It eliminates possibility of Loss of Cooling Accident (LOCA); moreover the technology allows swift removal of heat produced during normal or accidental conditions. Heavy Water Reactors (HWRs) are also in operation, however, the design process of improving emergency cooling system is ongoing. The design of Supercritical Water Reactor (SCWR) based on Canadian HWR is reviewed including the ongoing development in novel leakage detection method and material improvement. Liquid Metal Cooled Reactors (LMCR) are in advanced stage of research and development focusing on lead and sodium as the coolants. LMCR are secured from LOCA accidents due to low operating pressure and integration of the most elements in RPV. In case of Advanced Gas-Cooled Reactors (AGCR) the literature indicates several possible system integrations related to high operating temperature under development. AGCRs are able to use fully passive systems during all events due to their low power density. Furthermore, it is noted that the use of innovative reactor designs can mitigate proliferation concerns to an acceptable level. The authors identify the common research trend among all designs as the fuel cycle evaluation and optimization.

Small and Medium sized Reactors (SMR): A review of technology

Challenges in low-Prandtl number heat transfer simulation and modelling

Assessment and calibration of an algebraic turbulent heat flux model for low-Prandtl fluids

Development of fast breeder reactor technology in India

Eighteen sodium-cooled fast reactors (SFRs), a number that includes reactors in operation or shut down, have provided 388 reactor-years of operating experience to date. This paper summarizes the important incidents related to fast reactor sodium components and systems. The solutions incorporated, based on experience, analysis, experimental tests, and research and development for past and current SFRs, are described. The paper also describes lessons learned for future SFRs.

C.P. Pillai

Papers

The design of the prototype Fast Breeder Reactor