1-20 of 25
Keywords: sodium-cooled fast reactor
Close
Follow your search
Access your saved searches in your account

Would you like to receive an alert when new items match your search?
Close Modal
Sort by
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...
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
Paper No: ICONE28-64099
... the diversity and robustness of prevention measures for core disruptive accidents in sodium-cooled fast reactors. The proposed device contains pins with a fuel material that is kept in the solid state during normal operation but melts into the liquid when its temperature exceeds a prescribed value under...
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
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...
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, V003T12A003, August 4–6, 2021
Paper No: ICONE28-62252
...Abstract Abstract The eutectic reaction between boron carbide (B 4 C) and stainless steel (SS) is one of the most important phenomena when considering the core disruptive accident (CDA) in a sodium-cooled fast reactor (SFR). Thus, in order to perform the safety assessment of SFR under...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A009, August 4–6, 2021
Paper No: ICONE28-63298
...Abstract Abstract Sodium fire accident which was caused by the leakage of liquid sodium is the design basis accidents of sodium-cooled fast reactor. The column flow is a more realistic form of liquid sodium leakage due to the pipe system insulation structure and lower pressure in the sodium...
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, V003T12A025, August 4–6, 2021
Paper No: ICONE28-64500
... on contributed to effective cooling of molten alumina. fragmentation and cooling behavior of molten core material Keywords: sodium-cooled fast reactor, core disruptive discharged into regions where the depth and volume of sodium accident, molten core material, shallow sodium pool, fragmentation are limited...
Topics: Cooling, Sodium
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, V003T12A008, August 4–6, 2021
Paper No: ICONE28-63301
...Abstract Abstract One of the key issues in a core disruptive accident (CDA) evaluation in sodium-cooled fast reactors is eutectic reactions between boron carbide (B 4 C) and stainless steel (SS) as well as its relocation. Such behaviors have never been simulated in CDA numerical analyses...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A002, August 4–6, 2021
Paper No: ICONE28-61469
... Energy Agency to demonstrate the effectiveness of fuel discharge specific enthalpy from a fuel subassembly with an inner duct structure during a thermal conductivity core disruptive accident in a sodium-cooled fast reactor. The temperature experimental results suggested that early duct wall failure...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A039, August 4–6, 2021
Paper No: ICONE28-64454
... dynamics. sodium-cooled fast reactor large leakage sodium-water reaction long-term effects pressure source secondary loop Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-64454 LONG-TERM SIMULATION OF SODIUM...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A048, August 4–6, 2021
Paper No: ICONE28-64490
...Abstract Abstract A pressure wave propagation across the second loop of a sodium-cooled fast reactor may lead to severe damage to the pipes and the equipment due to a large leakage sodium-water reaction accident. Therefore, the pressure source and the pressure wave propagation calculation...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A004, August 4–5, 2020
Paper No: ICONE2020-16075
...Abstract Abstract In a postulated severe accidental condition of sodium-cooled fast reactor (SFR), eutectic melting between boron carbide (B 4 C) as control rod element and stainless steel (SS) as control rod cladding or related structure may take place. Thus, kinetic behavior of B 4 C-SS...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A007, August 4–5, 2020
Paper No: ICONE2020-16102
...STUDY ON EUTECTIC MELTING BEHAVIOR OF CONTROL ROD MATERIALS IN CORE DISRUPTIVE ACCIDENTS OF SODIUM-COOLED FAST REACTORS: (1) PROJECT OVERVIEW AND PROGRESS UNTIL 2018 Hidemasa Yamano1, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama Japan Atomic Energy Agency (JAEA) 4002...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A028, August 4–5, 2020
Paper No: ICONE2020-16440
...Abstract Abstract In order to improve the safety of nuclear power plants, it is necessary to make sure measures against their severe accidents. Especially, in the case of a sodium-cooled fast reactor (SFR), there is a possibility of significant energy release due to formation of a large-scale...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A048, August 4–5, 2020
Paper No: ICONE2020-16818
... by the CONTAIN-LMR code. The ex-vessel module was applied to the computation assuming sodium leak from a reactor vessel and a primary cooling loop. This computation demonstrated increase of temperature and pressure due to sodium-concrete interaction and sodium fire. Keywords: Sodium-cooled fast reactor, Severe...