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1-20 of 26
Keywords: Steam Generator
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Proceedings Papers
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A003, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131874
... Abstract The Helical-tube Once-through Steam Generator (H-OTSG) is a crucial component of the gas-cooled reactor, with the helical heat exchanger tube in the H-OTSG forming an integral part of the reactor’s primary pressure boundary. The volumetric in-service inspection of this helical heat...
Proceedings Papers
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132379
...-entrainment phenomenon and provides important reference for the design of corrugated plate dryers in nuclear power plants and nuclear power plants. steam-liquid separation steam generator liquid film breakdown model corrugated plate dryer Proceedings of the 2024 31st International Conference...
Proceedings Papers
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A017, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134975
... Abstract The structural integrity and safety of a steam generator are susceptible to flow-induced vibration. However, due to the intricate internal structure and thermal dynamics of the pressurized water reactor steam generator. Investigating the flow field characteristics and flow-induced...
Proceedings Papers
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A039, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135643
... Abstract In order to study the deposition and distribution of Fe 3 O 4 fouling and its impact on the thermal performance of steam generator (SG), numerical simulation model of SG has been developed based on porous medium model. The impact of Fe concentration of feed water on the fouling...
Topics:
Boilers
Proceedings Papers
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A056, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135345
...Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024, Prague, Czech Republic ICONE31-135345 INVESTIGATING THE MOTION CHARACTERISTICS OF COMPLEX-SHAPED FOREIGN OBJECTS ON THE SECONDARY SIDE OF A STEAM GENERATOR BASED ON CFD-DEM METHOD Defang Mu Xi...
Proceedings Papers
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A007, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91363
... by the components fabrication for nuclear power industry in the People’s Republic of China, this paper takes the qualification of dissimilar metal joint between inlet-nozzle and safe end of steam generator in Generation III nuclear power unit as an example, taking a comparative approach, compares the requirements...
Proceedings Papers
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A078, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92316
... Abstract As the largest heat exchange equipment in the nuclear power plant system, steam generator (SG) is mainly responsible for the heat transfer matching between reactor coolant system (RCS) and secondary system in normal operation. The steam generator incorporating U type heat transfer tube...
Proceedings Papers
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A045, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92553
... Abstract Ocean conditions can cause the steam generator in nuclear-powered ship to heave, sway and tilt with the ship, causing the free liquid surface in the steam generator to fluctuate and causing additional fluctuations of pressure and water level. In this paper, the CFD method is used...
Proceedings Papers
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A087, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93629
... Abstract The steam generator tubes in PWR unit are prone to mechanical damage and corrosion hazard, tube cracks and steam generator leakage often occurs on alloy 600 tubes. Due to the better corrosion resistance of alloy 690, the tube leakage has never occurred in CPR1000 unit. However, based...
Proceedings Papers
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A063, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91880
... Abstract Steam generator (SG) is an important equipment of the nuclear power plant, and the stability of its liquid level affects the safe operation of the nuclear power plant. SG is a complex system with nonlinear, time-varying, nonminimum-phase, small stability margin and large time delay...
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, V001T04A007, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64168
... Abstract The integrated small modular reactors (SMR) have been attracting more and more attentions in the field of nuclear energy. For PWR-type SMR with full-power natural circulation, a built-in steam generator with high heat transfer performance is required to enhance the natural circulation...
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
... 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...
Proceedings Papers
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 771-780, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55232
... A method of reprocessing coal slag and ash into granulate for the building industry in a combined wasteless aggregate – steam-generator/melting-converter was developed and tested. The method involves melting slag and ash from coal-fired team-generators of thermal-power plants in a melting...
Proceedings Papers
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 151-155, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54397
..., Sapporo, Japan Phone:+81-11-706-7842 k.hide.16@eng.hokudai.ac.jp Ken-ichiro SUGIYAMA Hokkaido University North13 West8, North Ward, Sapporo, Japan Phone:+81-11-706-7842 k-sugi@eng.hokudai.ac.jp Keywords: Sodium-water reaction, SFBR, Steam generator, Heat transfer, Reaction products, Adhesion. ABSTRACT...
Proceedings Papers
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 517-523, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29502
... steam generator natural circulation reverse flow RELAP5/MOD3.3 1Proceedings of the 18th International Conference on Nuclear Engineering ICONE18 May 17-21, 2010, Xi'an, China ICONE18-29502 DR ASYMMETRY INVESTIGATION ON SINGLE PHASE FLOW IN INVERTED U-TUBES OF STEAM GENERATOR UNDER...
Proceedings Papers
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 617-624, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29930
... 08 04 2011 Investigations on Optimal Design of a U-tube Steam Generator QIN Hui-min,YAN Chang-qi, WANG Meng,HE Shi-jing College of Nuclear science and technology, Harbin Engineering University, 150001, China Key words Steam Generator, Optimal Design; Sensitivity Analysis Abstract Steam...
Proceedings Papers
V. Prakash, M. Thirumalai, P. Murugesan, V. Vinod, V. A. Sureshkumar, I. B. Noushad, K. K. Rajan, P. Kalyanasundaram, G. Vaidyanathan
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 315-321, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48253
... in an operating plant. If the flow oscillation in the tube manifests itself in the overall module flow, then fluctuation in the overall flow/flow noise could be utilized for on-line stability measurements. Towards this, experiments were conducted in the sodium heated once through steam generator in an OTSG model...
Proceedings Papers
Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 955-960, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48768
... distribution of void fraction in the sodium pool. 09 07 2009 FBR Steam generator Sodium-water reaction Void fraction Proceedings of the 16th International Conference on Nuclear Engineering ICONE16 May 11-15, 2008, Orlando, Florida, USA 1 Copyright © 2008 by ASME Phone & Fax :+81-11-706...
Proceedings Papers
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 983-990, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22570
... IRIS concept. The ongoing design activity about the steam generator is the subject of this paper. IRIS Steam generator Helical coil Generation IV In service inspection Proceedings of ICONE-10 10th International Conference on Nuclear Engineering l t NERI contain includi generat elimina...
Topics:
Boilers
Proceedings Papers
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 105-113, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22099
... 05 03 2009 The steam generator (SG) in a pressurized water reactor (PWR) is an important component as boundary between the primary loop and the secondary loop. In this study, we performed two-phase flow analysis of SG reliability tests conducted by the Nuclear Power Engineering...
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