The Water-Cooled Lithium–Lead (WCLL) is one of the most promising technologies for power conversion and tritium production in future fusion-powered reactors; it will be implemented Test Breeding Modules (TBM) inside ITER reactor DEMO EU reactor. However, simultaneous presence system high-temperature PbLi high-pressure water poses significant safety issues event an in-box LOCA (Loss Of Coolant A...

Abstract Safety analyses for nuclear power plants were carried out in the past using a conservative approach. With increase of phenomenological knowledge, through experimental data, and computational power, it became possible to adopt best estimate thermal- hydraulic system codes perform deterministic safety analyses. However, some uncertainties are still present models, correlations, initial b...

This study explores the root causes of Fukushima Daiichi disaster and discusses how complexity tight coupling in large-scale systems should be reduced under emergencies such as station blackout (SBO) to prevent future disasters. First, on basis a summary published literature disaster, we found that direct (i.e., malfunctions problems) included overlooking loss coolant nuclear reactor’s failure ...

Tip leakage loss introduces major part of losses of the rotor in axial gas turbines. Therefore, the rotor blade tip has a considerable effect on rotor efficiency. To understand the flow physics of the rotor tip leakage, we solve the flow field for different tip platforms (passive flow control) and by considering coolant tip injection (active flow control). Various blade tip configurations s...

Robustness analysis is an emerging field in the uncertainty quantification domain. It involves analyzing response of a computer model—which has inputs whose exact values are unknown—to perturbation one or several its input distributions. Practical robustness methods therefore require coherent methodology for perturbing distributions; we present here such rigorous method, based on Fisher distanc...

The in-box LOCA (Loss of Coolant Accident) represents a major safety concern to be addressed in the design WCLL-BB (water-cooled lead-lithium breeding blanket). Research activities are ongoing master phenomena and processes that occur during postulated accident, enhance predictive capability reliability numerical tools, validate computer models, codes, procedures for their applications. Followi...

After the Fukushima Daiichi Accident, safety features such as accident tolerant fuel (ATF) and diverse flexible coping strategies (FLEX) for existing nuclear fleets are being investigated by US Department of Energy under Light Water Reactor Sustainability Program. This research is conducted to quantify risk-benefit these features. Dynamic probabilistic risk assessment (DPRA)-based response-surf...

After the accident in Fukushima Daiichi NPP, Nuclear Energy Agency Committee on Safety of Installations (OECD/NEA CSNI) initiated activities to address some technical issues. As a one results, Status report Spent Fuel Pools (SFPs) under Loss Cooling Accident Conditions was created. To give valuable contribution post-Fukushima decision making process, brief summaries were produced on:
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Abstract This paper deals with experimental tests of steam condensation in a water pool at atmospheric pressure and temperature the range 15-100 °C. The activity is performed frame research program, funded by ITER organization, for study dust deposition, produced Vacuum Vessel entrained non condensable gas into Pressure Suppression Tanks case Loss Coolant Accident. subcooled has been investigat...