KOSEN 한인과학기술자네트워크

ICONE 국제 학회는 ASME 주관하는 원자력안전분야의 큰 규모의 학회로써, 총 20개 분야의 많은 전문가들이 모여서 논문를 발표하고, 연구성과를 논의하고 있음.
ICONE 학회는 ASME 주관아래 1991년 부터는 일본 기계학회와 2005년 이후에는 중국원자력학회의와 공동으로 개최하고 있음.
본 학회를 통해서 전세계의 원자력 분야의 기술개발 및 발전현황을 소개하고 있으며 원자력 산업의 중요성을 전파하고 있음.

학회 발표 분야는 다음과 같음.

Track 1 Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant
Track 2 Nuclear Fuel and Materials
Track 3 Plant Systems, Structures and Components
Track 4 Radiation Protection and Nuclear Technology Applications
Track 5 Next Generation Reactors and Advanced Reactors
Track 6 Nuclear Safety and Security
Track 7 Codes, Standards, Licensing and Regulatory Issues
Track 8 Fuel Cycle, Radioactive Waste Management and Decommissioning
Track 9 Thermal Hydraulics
Track 10 Computational Fluid Dynamics (CFD) and Coupled Codes
Track 11 Reactor Physics and Transport Theory
Track 12 Nuclear Education, Public Acceptance and Related Issues
Track 13 Instrumentation and Controls (I&C)
Track 14 Fusion Engineering
Track 15 Beyond Design Basis Events
Track 16 Innovative Nuclear Power Plant Design and New Technology Application
Track 17 Student Paper Competition
Track 18 Industry Forum: Keynote, Plenary, and Panel Sessions
Track 19 Workshops and Professional Development Seminar
Track 20 Nuclear Codes & Standards Workshop

신청인은 본 학회에 논문을 발표하면서 한국원자력연구원에서 수행하고 있는 중수로 감속재 순환유동실험 (MCT) 장치, PIV 유동장 측정 및 해석결과를 소개하고, 관련 전문가들의 의견을 수렴하고자 함.

논문 제목:Experimental Study of Moderator Circulation in CANDU6 Calandria Tank

논문 초록: As a CANDU6 reactor has a high pressure primary cooling system and an independently cooled moderator system, the moderator in the calandria would act as a supplementary heat sink during a loss of coolant accident (LOCA) if the primary cooling and emergency coolant injection systems fail to remove the decay heat from the fuel. For the safety concern it is required to predict the 3-dimensional velocity and temperature distribution of moderator fluid to confirm the effectiveness of moderator heat sink.
Korea Atomic Energy Research Institute (KAERI) is carrying out a scaled-down moderator test program to simulate the CANDU6 moderator circulation phenomena during steady state operation and accident conditions. This research program includes the construction of the Moderator Circulation Test (MCT) facility, production of the validation data for self-reliant CFD tools, and development of optical measurement system using the Particle Image Velocimetry (PIV). In the present work the PIV technique is used to measure the velocity distributions in the scaled moderator tank of MCT under iso-thermal test conditions and these PIV measurement data are compared with a CFX code predictions.