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Development of Sweepout Model in APR1400 during an LBLOCA
Nuclear Science and Engineering, 2006As a result of experiments with the Upper Plenum Test Facility and the 1400-MW(electric) Advanced Power Reactor (APR1400), sweepout in the downcomer has been identified as playing an important role...
Byoung-Uhn Bae +2 more
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APR1400: Evolutionary Korean Next Generation Reactor
10th International Conference on Nuclear Engineering, Volume 2, 2002Following the Korean Standard Nuclear Power Plant (KSNP) program which has shown its success through operation of its first units, Ulchin 3&4, Korean nuclear industry, with the support of Korean government, has launched its next program to develop 4000MWt (1400MWe) Advanced Power Reactor, APR1400, as a Korean next generation reactor.
Insik Kim, Dong-Su Kim
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Air Clearing Oscillation Produced by APR1400 Prototype Sparger
Thermal Hydraulic Problems, Sloshing Phenomena, and Extreme Loads on Structures, 2002KAERI has performed a series of experiments to investigate the performance of APR1400 prototype sparger in view of the dynamic load oscillation with the variation of test conditions such as discharged air mass, submergence of the sparger, valve opening time, and pool temperature during the air-clearing phase.
Seok Cho +5 more
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Severe Accident Mitigation Features of APR1400
2010The APR1400 (advanced power reactor, 1,400 MWe) is a standard advanced evolutionary light water reactor (ALWR) in the Republic of Korea. It is now under construction as Shin-Kori units 3 and 4. The APR1400 is designed with an additional safety margin to improve the protection of the public health, mainly focusing on typical initiators such as ...
Sang-Baik Kim, Seung-Jong Oh
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Performance Improvement of Liquid Waste Management System for APR1400
Progress in Nuclear Energy, 2017Abstract The Liquid Waste Management System (LWMS) is a radioactive waste storage and treatment facility equipped in the nuclear power plants to ensure the safe management of radioactive waste generated in the process of operation. New and improved materials and processes are continuously under consideration and development in various countries to ...
Ji-Min Kim, Chang-Lak Kim
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Development of Best-Estimate ECCS Evaluation Methodology for APR1400
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 2009Advanced Power Reactor 1400 (APR1400) is an evolutionary Pressurized Water Reactor (PWR) equipped with such advanced features as the Direct Vessel Injection (DVI), the Fluidic Device (FD) in the Safety Injection Tank (SIT), and the In-containment Refueling Water Storage Tank (IRWST) in the Emergency Core Cooling System (ECCS). To verify the performance
Seok-Ho Lee, Mun-Soo Kim, Han-Gon Kim
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The Development of Impact Analysis Methodology for CEDM Missile of APR1400
Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 2009The paper deals with the impact analysis methodology for control element drive mechanism (CEDM) missile of advanced Power Reactor 1400 (APR1400). The methodology includes the development of jet expansion models to develop the missile velocity as well as the missile impact analysis itself and the application of Fauske model to obtain jet velocity in two-
Tae Kyo Kang +3 more
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Fuel assembly design for APR1400 with low CBC
AIP Conference Proceedings, 2015APR 1400 is a PWR (Pressurized Water Reactor) with rated power of 3983 MWth and 241 assemblies. Recently, demand for extremely longer cycle up to 24 months is increasing with challenge of higher critical boron concentration (CBC). In this paper, assembly design method of selecting Gd-rods is introduced to reduce CBC.
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Structural analysis of CSB and LSS for APR1400 RVI CVAP
Nuclear Engineering and Design, 2013Abstract The study of the integrity of reactors has become an important aspect regarding the safety of nuclear power plants. The US Nuclear Regulatory Commission Regulatory Guide (NRC RG) 1.20 requires a comprehensive vibration assessment program (CVAP) to be used when verifying the structural integrity of the reactor vessel internals (RVI) for flow ...
Do Young Ko, Kyu Hyung Kim
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Development of passive flow controlling safety injection tank for APR1400
Nuclear Engineering and Design, 2008A vortex valve, called fluidic device, is to be installed inside a Safety Injection Tank (SIT) of Advanced Power Reactor 1400 MWe (APR1400) that passively controls an Emergency Core Cooling (ECC) water discharge flow rate without any moving part or any action of the plant operator. The fluidic device was designed, and its performance was evaluated by a
In-Cheol Chu +3 more
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