... a good match with the prototype, which can be used to study the key phenomena and safety characteristics of the safety system and confirm the effectiveness of the safety design of AHPR1000. safety system proportion analysis test facility SBLOCA safety analysis Proceedings of the 2024 31st...

... operational characteristics were investigated under small break loss of coolant accident (SBLOCA). The simulation results demonstrated that the RELAP5 model can simulate the transient key system parameters accurately. This paper investigates the operational characteristics of the emergency core cooling system...

... PCCS SBLOCA response surface Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024, Prague, Czech Republic ICONE31-134863 RELIABILITY QUANTIFICATION OF PASSIVE CONTAINMENT COOLING SYSTEM THROUGH RESPONSE SURFACE METHODOLOGY Shikang Chen Ronghua Chen...

...Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-92128 PILOT APPLICATION OF RISMC METHODOLOGY ON SPECIFIC SBLOCA SEQUENCES OF PASSIVE NPP Yun Du1,2 1.Shanghai Jiao Tong University, Shanghai, China 2.Shanghai Nuclear...

... and analyze the severe accident of IP200 reactor caused by SBLOCA superimposed by the emergency power failure. Based on the steady state calculation, which agrees well with designed values, the SBLOCA accident for transient calculation started. First, the SBLOCA accident without the passive core cooling...

... Abstract The small break loss of coolant accident (SBLOCA) is a typical accident in the nuclear power plant, and the diagnosis of accident parameters in a small break loss of coolant accident (SBLOCA) is a very important research direction in the field of nuclear safety. The timely and accurate...

.... These preliminary analyses give valuable insight to the design work in the future. SMR Apros district heating transient SBO SBLOCA decay heat removal Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-64163 A FINNISH...

... 1 Copyright © 2013 by ASME VALIDATION OF TRACE CODE AGAINST ROSA/LSTF TEST FOR SBLOCA OF PRESSURE VESSEL UPPER-HEAD SMALL BREAK Mian Xing Division of Advanced Nuclear Energy Technology, State Nuclear Power Reseach Institute, SNPRI Beijing, China Xiao Hu State Nuclear Power Technology Corporation...

... Study on the Influence of Safety Injection Rate on the Process of SBLOCA He Hui Department of Nuclear Engineering, Chongqing University Chongqing 400044, China Liang-ming Pan Department of Nuclear Engineering, Chongqing University Chongqing 400044, China Abstract After the nuclear accident of TMI...

... In the framework of CAMP and OECD/NEA ROSA projects a broad analysis of Lower Head SBLOCA with High Pressure Safety Injection (HPSI) unavailable in a Westinghouse PWR has been performed. The simulations have been performed with TRACE 5 patch1 and the selected methodology has been the Integrated...

... In the transients produced during Small Break Loss-Of-Coolant Accidents (SBLOCA), the maximum Peak Cladding Temperature (PCT) in the core could suffer rapid excursions which might strongly affect the core integrity. Most Pressurized Water Reactors (PWR) have Core Exit Thermocouples (CETs...

... MARS-KS Assessment ATLAS 6-inch Cold Leg Break Test SBLOCA An integral effect test on the SBLOCA (Small-Break Loss of Coolant Accident) aiming at 6-inch cold leg bottom break, SB-CL-09, was conducted with the ATLAS on November, 13, 2009 by KAERI. In this study, the calculations using...