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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
Paper No: ICONE28-64168
...Abstract 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...
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
... Takata1, Sunghyon Jang3 1Japan Atomic Energy Agency, Oarai, Ibaraki, Japan 2NESI Corporation, Ibaraki, Japan 3University of Tokyo, Tokyo, Japan ABSTRACT Dbreak diameter of a discharging nozzle (m) For safety assessment or design of a steam generator (SG) Fd interfacial drag force (N) Fb buoyancy force (N...
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
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...
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
Paper No: ICONE20-POWER2012-54397
... A safety assessment on Sodium-Water reaction in a steam generator (SG) of the SFBR is also one of significant issue. If a heat transfer tube is damaged by some reasons, the high pressure water or steam would leak into the sodium side as a high-temperature and high-corrosive sound-speed jet...
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 517-523, May 17–21, 2010
Paper No: ICONE18-29502
...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 THE CONDITION OF NATURAL CIRCULATION WANG Chuan YU Lei Department of Nuclear...
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 617-624, May 17–21, 2010
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...
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
Paper No: ICONE16-48253
... 09 07 2009 Hydrodynamic flow instability in Once Through Steam Generators (OTSG) is one of the important problems in the design and operation of Liquid Metal Fast Breeder Reactors (LMFBRs). Under certain operating conditions, water flow in OTSG is susceptible to instability due...
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
Paper No: ICONE16-48768
... 09 07 2009 The occurrence of secondary heat transfer tube failure due to overheating by sodium-water reaction in LMFBR steam generators has been concerned from the viewpoint of public acceptance. To evaluate the phenomena for the secondary heat transfer tube failure, a sophisticated...
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 217-225, April 14–18, 2002
Paper No: ICONE10-22139
... 05 03 2009 Steam generators placed in service in the 1960s and 1970s were primarily fabricated from mill-annealed Alloy 600. Over time, this material proved to be susceptible to stress corrosion cracking in the highly pure primary and secondary water chemistry environments...
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 983-990, April 14–18, 2002
Paper No: ICONE10-22570
... lifecycle costs, design and cturing experience, and high reliability, a helical-coil ndle steam generator (SG) was selected. The helical-coil undle is a proven design that has operated in various s, including the French LMFBR Superphénix. There is e ten years (1968-1979) operating experience...
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 105-113, April 14–18, 2002
Paper No: ICONE10-22099
... analysis of SG reliability tests [1, 2] c by NUPEC, which were sponsored Ministry of International Trade and TWO PHASE FLOW ANALY IN STEAM G Y. YAGIM. MURASE, Institute of Nuclear Saf 64 Sata, Mihama-cho, Mika Tel81-770-37-9110 *e-mail: ya Key Words: Steam Generator...
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 199-203, April 14–18, 2002
Paper No: ICONE10-22069
... 05 03 2009 This paper presents insights obtained from a study of the steam generator aging management at selected U.S. nuclear plants. The primary objective of this study was to conduct an in-depth review of the current steam generator (SG) management practices at selected U.S. nuclear...
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 783-789, April 25–29, 2004
Paper No: ICONE12-49403
... 25 11 2008 The tube rupture accident is one among the most risk-dominant events at the nuclear power plants. Several steam generator tube rupture accidents have occurred at the plants in the past. In this paper the Computational Multi-Fluid Dynamics (CMFD) investigation...
Hirofumi Ohashi, Tetsuo Nishihara, Tetsuaki Takeda, Yukimasa Maeda, Hiroyuki Sato, Yoshitomo Inaba, Koji Hayashi, Shoji Takada, Yoshiyuki Inagaki
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 507-514, April 25–29, 2004
Paper No: ICONE12-49419
... 25 11 2008 Japan Atomic Energy Research Institute has been developing a hydrogen production system coupling with the High Temperature Engineering Test Reactor (HTTR). In the design of a HTTR hydrogen production system, a steam generator (SG) is installed at the downstream of a chemical...
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 545-550, April 25–29, 2004
Paper No: ICONE12-49241
... 25 11 2008 A steam generator of PWR plant has moisture separators with function to separate water from two-phase flow of water and steam. Recently, corresponding to the request for power uprating of current and/or future plants with large thermal capacity, development of high...
Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 99-106, July 17–20, 2006
Paper No: ICONE14-89109
... a numerical model for the analysis of flow-induced instabilities in forced-convection steam generator. The model is based on the assumption of homogenous two-phase flow and thermodynamic equilibrium of the phases. The thermal capacity of the heater wall has been included in the analysis. The model is used...