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Keywords: sodium-cooled fast reactor
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Proceedings Papers

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90542
... 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 is one of the important points when considering rationalization of maintenance. Therefore, we previously proposed a maintenance...
Proceedings Papers

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89908
... of Atomic Energy Beijing, China 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A021, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91847
... 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A022, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91857
... 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A025, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92109
... 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91812
... 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A001, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88933
... 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A037, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93169
... 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 heat transfer phenomenon under decay heat discharged accident condition...
Proceedings Papers

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A030, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91901
... 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A007, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90288
... sodium-cooled fast reactor gas entrainment unsteady vortices vortex center line pressure decrease 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...
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-61345
... sodium-cooled fast reactor steam generator LEAP-III Lagrangian particle method engineering approach 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...
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A005, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63380
... 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...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T08A013, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64755
... 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...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-61200
... Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-61200 EXPERIMENTAL STUDY ON AEROSOL TRANSPORT BEHAVIOR IN MULTIPLE CELLS WITH EXPANDABLE CONNECTING PIPE FOR SAFETY ASSESSMENT OF SODIUM-COOLED FAST REACTORS Ryota Umeda...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T08A007, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64515
... fast reactor adopts a new type the sodium-cooled fast reactor. The forced circulation and natural circulation are driven in different ways and specific of decay heat removal method to discharge the core heat to phenomena may occur in the coolant core flow. So it is necessary ensure the safety and cool...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A013, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64099
... under expected device conditions. shutdown system (SASS) and the gas expansion module (GEM), have been developed and investigated in addition to active Keywords: Sodium-cooled fast reactor, Core disruptive reactor shutdown systems [1]. Then, in order to prevent large accident, Severe-accident prevention...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T08A019, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65662
... distributions appearing around the inner duct between the numerical results by ASFRE and those by V component of velocity [m/s] SPIRAL. z height [m] Keywords: Sodium-cooled Fast Reactor, Fuel Assembly, FAIDUS, Subchannel Analysis, Design by Analysis Greek Letters [K] T temperature increase (Eq. (2)) [rad...