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서정수,김한곤,Suh, Jungsoo,Kim, Han Gon 대한기계학회 2015 대한기계학회 논문집. Transactions of the KSME. C, 산업기술과 혁신 Vol.3 No.3
노내계측계통의 설치 위치 및 케이블의 관통위치가 중대사고 대처계통에 미치는 영향을 노내 노심용융물 억류 및 원자로용기 외벽냉각 전략과 노외 노심용융물 냉각계통을 중심으로 조사하였다. 기존에 국내원전에서 주로 사용되었던 노내계측계통의 원자로 용기 하부탑재 및 ICI케이블의 원자로 용기하부 관통이 중대사고에 미치는 영향을 정리하고, 이러한 단점을 개선하기 위해 노내계측계통의 ICI 케이블이 원자로 용기 상부를 관통하는 상부탑재 노내계측계통의 장점을 기술하였다. The effects of the mounting location of ICI cables on severe accident mitigation systems, specially IVR-ERVC (In-Vessel Retention by External Reactor Vessel Cooling) and core catcher (Ex-vessel corium retention and cooling system), are investigated. The effects of bottom-mounted ICI strategy on severe accident mitigation are summarized and advantages of top-mounted ICI to improve severe accident mitigation are also highlighted.
ANSYS CFX 를 이용한 Marviken 자유 제트유동 실험의 전산모사 현황
서정수(Jungsoo Suh),하희운(Huiun Ha) 대한기계학회 2019 대한기계학회 논문집. Transactions of the KSME. C, 산업기술과 혁신 Vol.7 No.1
원자력발전소의 안전계통은 주위 배관의 파단에 따른 동적 영향으로부터 보호되도록 설계되어야 하며, 이를 위하여 원자력발전소의 고에너지 배관 파단에 의한 하중평가가 필요하다. 본 논문에서는 기존에 사용되었던 파단된 배관으로부터의 제트의 충돌하중 평가방법론이 압축성 유동 특성을 반영하지 못 하는 등 비보수적이라는 지적에 따라 전산유체역학을 이용한 새로운 해석방법론을 검토하고, 그 첫번째 단계로 Marviken 실험 중 자유제트 유동을 모사한 내용을 소개한다. Safety systems at nuclear power plant should be designed to protect dynamic effect from neighboring line break. Therefore the load from high energy line break should be evaluated carefully. New analysis methodology using computational fluid dynamics was investigated for jet impingement from high energy line break in order to substitute the previous analysis methodology which did not consider compressible flow phenomena sufficiently. As the first step of the present work, free jet flow from Marviken experiment was simulated.
서정수(Jungsoo Suh),김한곤(Hangon Kim) 대한기계학회 2013 대한기계학회 춘추학술대회 Vol.2013 No.12
EU-APR1400, the Korean nuclear reactor design for European market adopts a so-called core catcher for ex-vessel molten corium retention and cooling as a severe-accident mitigation system. Sacrificial material, which controls melt properties and modifies melt conditions favorable for corium cooling and retention, is usually employed to protect core catcher body from molten corium. Since molten corium can be ejected through a breach of a reactor pressure vessel and impinged on the sacrificial material with enhanced heat transfer at a severe accident, it is very important to predict ablation rate of sacrificial material due to corium jet impingement accurately for core catcher design. In this paper, sacrificial-material ablation model based on boundary layer theory is suggested and compared with the experimental results by KAERI.
직접냉각방식 및 간접냉각방식 Core Catcher의 성능비교
서정수(Jungsoo Suh),이종호(Jong Ho Lee),배병환(Byung Hwan Bae) 대한기계학회 2012 大韓機械學會論文集B Vol.36 No.10
유럽지역으로의 원전 수출을 위해서는 유럽의 원전 인허가요건을 충족시켜야 하며, 이에 따르면 원전의 중대사고 대처설비로 통상 Core Catcher로 불리는 노외 노심 용융물 냉각설비를 갖출 것을 권장하고 있다. 이에 따라 본 논문에서는 노심 용융물 직접냉각방식과 간접냉각방식에 대해 각각의 개념 안의 장/단점을 비교, 검토하였으며, 그 결과 직접냉각방식은 냉각효율 측면에서, 간접냉각방식은 중대사고 사고관리 측면에서 각각 우위를 보였다. The European nuclear design requirements, which should be satisfied by nuclear reactors in Europe, usually recommend a so-called core catcher, which is a molten core ex-vessel cooling facility, to manage a severe accident at a nuclear reactor. Two different types of core catcher concepts are compared to determine their abilities to manage severe accidents and cool core melts. The study reveals that direct cooling is better for cooling capacity and is convenient to construct, while indirect cooing is better for the management of a severe accident.
서정수 ( Jungsoo Suh ),하희운 ( Huiun Ha ) 한국안전학회 2017 한국안전학회지 Vol.32 No.2
The external reactor vessel cooling (ERVC) is well known strategy to mitigate a severe accident at which nuclear fuel inside the reactor vessel is molten. In order to compare the heat removal capacity of ERVC between the nuclear reactor designs quantitatively, numerical method is often used. However, the study for ERVC using computational fluid dynamics (CFD) is still quite scarce. As a validation study on the numerical prediction for ERVC using CFD, the subcooled boiling flow and natural circulation of coolant at the ULPU-V experiment was simulated. The commercially available CFD software ANSYS-CFX was used. Shear stress transport (SST) model and RPI model were used for turbulence closure and wall-boiling, respectively. The averaged flow velocities in the downcomer and the baffle entry under the reactor vessel lower plenum are in good agreement with the available experimental data and recent computational results. Steam generated from the heated wall condenses rapidly and coolant flows maintains single-phase flow until coolant boils again by flashing process due to the decrease of saturation temperature induced by higher elevation. Hence, the flow rate of coolant natural circulation does not vary significantly with the change of heat flux applied at the reactor vessel, which is also consistent with the previous literatures.
직접냉각방식 및 간접냉각방식 Core Catcher의 성능비교
서정수(Jungsoo Suh),이종호(Jong Ho Lee),배병환(Byung Hwan Bae) 대한기계학회 2011 대한기계학회 춘추학술대회 Vol.2011 No.10
The European nuclear design requirements, which should be satisfied with a nuclear reactor in Europe region, usually recommend so called core catcher, molten core ex-vessel cooling facility to manage severe accident at a high power nuclear reactor. Two different types of core catcher concepts are compared to determine their ability to manage severe accident and cool core melt and convenient to construct. The study reveals direct cooling is better for cooling capability and convenience to construct and indirect cooling is better for management of severe accident, respectively.
EU-APR1400 Core Catcher 용융물-희생물질 반응모델 개발 현황
서정수(Jungsoo Suh),김한곤(Han Gon Kim) 대한기계학회 2012 대한기계학회 춘추학술대회 Vol.2012 No.11
EU-APR1400, nuclear reactor design for European export market, adopts a so-called core catcher, which is a ex-vessel molten core cooling facility as a severe-accident mitigation system. Sacrificial material, which controls the melt properties and modifies melt conditions favorable to corium cooling and retention, is employed to protect core catcher body from melt core and increase its cooling capability. In this paper, the present status of numerical model development for corium - sacrificial material interaction, for the EU-APR1400 core catcher, is summarized. The reaction mechanism, which diverges according to the corium composition and its temperature, is proposed and its improvement plan is also discussed.
서정수(Jungsoo Suh),김한곤(Hangon Kim) 대한기계학회 2014 대한기계학회 춘추학술대회 Vol.2014 No.11
We investigated the effects of the mounting location of ICI cables on severe accident mitigation systems, specially IVR-ERVC (In-Vessel Retention by External Reactor Vessel Cooling) and core catcher (Ex-vessel corium retention and cooling system). Effects of bottom-mounted ICI strategy on severe accident mitigation are summarized and advantages of top-mounted ICI to improve severe accident mitigation are also highlighted.