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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
... In order to study the reverse flow characteristics in U-tubes of steam generator in the natural circulation case, the code RELAP5/MOD3.3 is used to model and calculate single-phase water flow for PWR under some typical operating conditions in the natural circulation case. The U-tubes of steam...
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 617-624, May 17–21, 2010
Paper No: ICONE18-29930
... Steam generator is one of the key equipments in the pressurized water reactor, from the performance point of view, it is necessary to apply optimization techniques to the design of the steam generator. In this work, the optimal designs of a U-tube steam generator (UTSG), taking minimization...
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...
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. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 199-203, April 14–18, 2002
Paper No: ICONE10-22069
... 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 plants. The plants...
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 983-990, April 14–18, 2002
Paper No: ICONE10-22570
... including the reactor core, the coolant pumps, the steam generators and the pressurizer. This integral design approach eliminates the large coolant loop piping, and thus eliminates large loss-of-coolant accidents (LOCAs) as well as the individual component pressure vessels and supports. In addition, IRIS...
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 105-113, April 14–18, 2002
Paper No: ICONE10-22099
... 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 Corporation (NUPEC) using...
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 217-225, April 14–18, 2002
Paper No: ICONE10-22139
... 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 of pressurized-water reactors...
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 545-550, April 25–29, 2004
Paper No: ICONE12-49241
... 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 performance moisture separator...
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
... 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 reactor, a steam...
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 783-789, April 25–29, 2004
Paper No: ICONE12-49403
... 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 of the horizontal steam generator...
Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 99-106, July 17–20, 2006
Paper No: ICONE14-89109
... 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 to analysis of flow...