.... Compared with DEC-B, the DEC-A is a newer concept, and the mature cognition of DEC-A has not yet been reached. The selection method of DEC-A for sodium-cooled fast reactor is analyzed systematically, which includes how to define, identify and screen DEC-A. Taking a sodium-cooled fast reactor as an example...

... is used to carry out the steady-state numerical simulation of a 7-pin sodium-cooled fast reactor wire-wrapped fuel bundle. The turbulent Prandtl number of liquid sodium is no longer approximate to the default value of 0.85. Kays model is used as a UDF of Fluent to modify the turbulent Prandtl number...

... Abstract In a sodium-cooled fast reactor (SFR), cover gas entrainment (GE) by vortices generated at the free surface in the upper plenum of the reactor vessel is one of the significant issues in the safety design and the development of an evaluation method for GE is required. A GE evaluation...

... Abstract Loading elevator is one of the important equipment for refueling system. The refueling process of the sodium-cooled fast reactor is sealed and the equipment for refueling process is complicated and in large quantity. It is necessary to research and develop a set of high-accuracy...

... Abstract In sodium-cooled fast reactors (SFRs), hydrogen is a major nonmetallic impurity in the coolant during normal operation. A higher hydrogen concentration than the gas-liquid equilibrium had been transiently detected in the gas space of the actual SFR plant. However, the chemical...

... on the core catcher and effectiveness of design measures. This study suggests that the criticality measure is very important for the core catcher study. sodium-cooled fast reactor severe accident core catcher debris criticality coolability Proceedings of the 2022 29th International Conference...

... extent. This research may provide the guidance for experiment configuration and the further study. sodium-cooled fast reactor load rejection emergency shutdown optimization Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online...

.... sodium-cooled fast reactor severe accident core catcher debris bed coolability Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-93244 COOLABILITY EVALUATION OF THE DEBRIS BED ON CORE CATCHER IN A SODIUMCOOLED FAST...

... Abstract As one of the GEN-IV nuclear reactor systems proposed by GEN-IV International Forum, the sodium-cooled fast reactor features the energy generation with fast spectrum and a closed fuel cycle for fuel breeding and actinide management. In order to validate system codes for reactor system...

... Abstract A new subassembly-type passive reactor shutdown device is proposed to expand the diversity and robustness of core disruptive accident prevention measures for sodium-cooled fast reactors (SFRs). The device contains pins with a fuel material that is in a solid state during normal...

... to thermal transient derived from shutdown. We confirmed that the procedure can evaluate the failure probability depending on the cylinder thickness with practical calculation cost. Keywords: Sodium-cooled fast reactor; FOSM; reliability index; failure probability; orthogonal table, design optimization...

... Abstract In order to develop rationalized maintenance plans of nuclear power plants, it is necessary to consider characteristics of each plant. For sodium-cooled fast reactor (SFR) plants, there are constraints on inspections due to the specialty that sodium equipment needs to be handled, which...

... Abstract If the plant blackout accident occurs in the pool-type sodium-cooled fast reactor, the decay heat of the core is discharged through natural circulation. The Plant Dynamics Test Loop (PLANDTL-DHX), an experimental device built in Japan, can simulate core coolant flow process and decay...

... not have a deep understanding of the theoretical concepts of nuclear power systems in class. For research and teaching work on Sodium-cooled fast reactor (SFR), the Department of Engineering Physics at Tsinghua University has developed the sodium-cooled fast reactor nuclear power plant simulation software...

... Abstract As a critical component for pool-type Sodium cooled Fast Reactor (SFR), the main vessel plays a major role in holding the entire sodium in the pool. While the Reactor Vessel Cooling System (RVCS) would contribute to the cooling of the main vessel. This paper develops a one-dimensional...

... Abstract For safety assessment or design of a steam generator (SG) of a sodium-cooled fast reactor, it is important to evaluate the effects of a multiphase flow involving sodium-water reaction. If pressurized water/water-vapor leaks from a tube, it forms a corrosive, high-temperature, and high...

... Abstract In order to enhance the safety of sodium-cooled fast reactors, a direct reactor auxiliary cooling system (DRACS) under natural circulation conditions with a dipped-type direct heat exchanger (D-DHX) in an upper plenum of the reactor vessel has been investigated. During the DRACS...

... effective it is to lower the maximum temperature of the coolant. The application of the variable-pitch helical wire can well match the demand of the coolant for thermal and hydraulic needs, and the safety and economy of the assembly can be correspondingly improved. sodium-cooled fast reactor test...

... Abstract Sodium fire is one of the accidental events in case of sodium leak of sodium-cooled fast reactor. This event is basically the reaction between liquid sodium and oxygen with exothermic heat. The transport behavior of the aerosol as reaction product (sodium oxide) by sodium fire through...

... Abstract The pool-type sodium-cooled fast reactor adopts a new type of decay heat removal method to discharge the core heat to ensure the safety and cool of the nuclear power plant in a long time under the station blackout accident. The natural circulation and forced circulation will lead...