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Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A058, August 8–12, 2022
Paper No: ICONE29-92874
... Abstract The primary circuit transient of nuclear power plant is one of the important references for characterizing the fatigue of primary circuit materials. For the classification of transients, the commonly used method is to determine the category of transients according to the change...
Mian Xing, Linsen Li, Gang Zheng, Junlang Wen, Chunyuan Liu, Yeoh Eing Yee, Zhen Luo, Peidong Sun, Jinjun Feng
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, V001T04A002, August 4–6, 2021
Paper No: ICONE28-63220
... reactor with LBE as the coolant, equipped with 8 helical tube steam generators and 4 primary pumps. The safety system consists of passive Decay Heat Removal System (DHR) and RVACS (Reactor Vessel Air Cooling System) outside the reactor vessel. For the preliminary transient analysis, the primary system...
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, V001T04A006, August 4–6, 2021
Paper No: ICONE28-64163
... in the integrated design. This paper presents the thermal-hydraulic design and transient analyses done with Apros simulation software. The studied cases include station blackout with reactor trip and as an ATWS scenario, and small break LOCA in the lower downcomer. During the station blackout transients, both...
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 401-405, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54788
... CHARACTERISTICS ANALYSIS OF SCWR DURING PARTIAL LOSS OF REACTOR COOLANT FLOW TRANSIENT Juan Chen North China Electric Power University Beijing, China Tao Zhou North China Electric Power University Beijing, China Zhousen Hou North China Electric Power University Beijing, China Canhui Sun North...
Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 83-90, July 17–20, 2006
Paper No: ICONE14-89204
... 17 09 2008 Spent fuel transportation casks are required to meet among others, the regulatory thermal test conditions in order to demonstrate their ability to withstand specified accidental fire conditions during transport. This paper describes the transient thermal analysis performed...