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Keywords: sodium-cooled fast reactor
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Proceedings Papers

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A041, August 8–12, 2022
Paper No: ICONE29-93065
.... 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...
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
Paper No: ICONE29-90542
... 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A008, August 8–12, 2022
Paper No: ICONE29-89908
... 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A021, August 8–12, 2022
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, V004T04A011, August 8–12, 2022
Paper No: ICONE29-91505
... 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A022, August 8–12, 2022
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 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A030, August 8–12, 2022
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
Paper No: ICONE29-90288
... 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A035, August 8–12, 2022
Paper No: ICONE29-93244
.... 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...
Proceedings Papers

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A025, August 8–12, 2022
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
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
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
Paper No: ICONE29-93169
... 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...
Proceedings Papers

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T01A005, August 4–6, 2021
Paper No: ICONE28-64364
... Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-64364 A SODIUM-COOLED FAST REACTOR SIMULATION SYSTEM AND ITS APPLICATION IN TEACHING RESEARCH BASED ON VPOWER PLATFORM Chengzhi JI1, Biheng XIE1, Xiaoyu GUO1, Wenbin HAN1...
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A012, August 4–6, 2021
Paper No: ICONE28-64293
... Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-64293 NUMERICAL ANALYSIS ON THE THERMAL-HYDRAULIC CHARACTERISTICS FOR THE REACTOR MAIN VESSEL COOLING SYSTEM OF CHINESE SODIUM COOLED FAST REACTOR Ping Song Tangtao Feng...
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A002, August 4–6, 2021
Paper No: ICONE28-61345
...) of a sodium-cooled fast reactor, it is important to evaluate the Fpt particle-tube interaction force (N) effects of a multiphase flow involving sodium-water reaction. If g gravity vector (m/s2) pressurized water/water-vapor leaks from a tube, it forms a N number of particles in a cell corrosive, high...
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A005, August 4–6, 2021
Paper No: ICONE28-63380
... Tanaka Japan Atomic Energy Agency O-arai, Ibaraki, JAPAN Yasuhiro Miyake, Yasutomo Imai NDD cooperation Mito, Ibaraki, JAPAN ABSTRACT NOMENCLATURE [m] In order to enhance the safety of sodium-cooled fast reactors, De hydraulic diameter f friction factor [m/s2] a direct reactor auxiliary cooling system...
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
Paper No: ICONE28-64755
... et al [10] discussed the reliability of different software, such as Star-ccm+, for SFR fuel Keywords: Sodium-cooled fast reactor; Test fuel bundle; assembly simulation, indicating that the K-w SST turbulence Variable-pitch; Helical wire; Thermo-hydraulic characteristics; model is more suitable...
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
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
Paper No: ICONE28-64515
...Abstract 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...