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AbstractAbstract
[en] Most advanced nuclear power plant designs adopted several kinds of passive systems. Natural circulation is used as a key driving force for many passive systems and even for core heat removal during normal operation such as NuScale, CAREM, ESBWR and Indian AHWR designs. Simulation of natural circulation phenomena is very challenging since the driving force of it is weak compared to forced circulation and involves a coupling between primary system and containment for integral type reactor. The IAEA ICSP (International Collaborative Standard Problem) on 'Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents' was proposed within the CRP on 'Natural Circulation Phenomena, Modelling, and Reliability of Passive Systems that utilize Natural Circulation'. Oregon State University (OSU) of USA offered to host this ICSP. This ICSP plans to conduct the following experiments and blind/open simulations with system codes: 1. Quasi-steady state operation with different core power levels: Conduct quasi-steady state operation with step-wise increase of core power level in order to observe single phase natural circulation flow according to power level. The experimental facility and operating conditions for an integral PWR will be used. 2. Thermo-hydraulic Coupling between Primary system and Containment: Conduct a loss of feedwater transient with subsequent ADS blowdown and long term cooling to determine the progression of a loss of feedwater transient by natural circulation through primary and containment systems. These tests would examine the blowdown phase as well as the long term cooling using sump natural circulation by coupling the primary to containment systems. This data could be used for the evaluation of system codes to determine if they model specific phenomena in an accurate manner. OSU completed planned two ICSP tests in July 2011 and real initial and boundary conditions measured from the tests were distributed to all ICSP participants for their blind calculations. Objective of ICSP: - Improve understanding of natural circulation phenomena expected to occur in integral type PWRs - Evaluate system code capabilities to predict natural circulation phenomena for integral type PWR, their practicality and efficiency, by simulating an integrated experiment - Supply experimental data for single/two-phase flow natural circulation instability and long-term cooling by natural circulation through coupled primary system and containment - Suggest necessary code improvements or new experiments to reduce uncertainties
Primary Subject
Secondary Subject
Source
Apr 2012; vp; 3. Workshop for IAEA ICSP on Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents; Daejeon (Korea, Republic of); 27-30 Mar 2012; Also available on-line: http://www.iaea.org/NuclearPower/Technology/Meetings/2012-03-27-30-WS-Korea.html
Record Type
Report
Literature Type
Conference; Numerical Data
Report Number
Country of publication
BOUNDARY CONDITIONS, CONTAINMENT SYSTEMS, COORDINATED RESEARCH PROGRAMS, DEPRESSURIZATION SYSTEMS, DESIGN, EFFICIENCY, EXPERIMENTAL DATA, FEEDWATER, LOSS OF COOLANT, NATURAL CONVECTION, PRIMARY COOLANT CIRCUITS, PWR TYPE REACTORS, REACTOR ACCIDENTS, RELIABILITY, SIMULATION, STEADY-STATE CONDITIONS, THERMAL HYDRAULICS, TRANSIENTS, TWO-PHASE FLOW
ACCIDENTS, CONTAINMENT, CONVECTION, COOLING SYSTEMS, DATA, ENERGY SYSTEMS, ENERGY TRANSFER, ENGINEERED SAFETY SYSTEMS, ENRICHED URANIUM REACTORS, FLUID FLOW, FLUID MECHANICS, HEAT TRANSFER, HYDRAULICS, HYDROGEN COMPOUNDS, INFORMATION, MASS TRANSFER, MECHANICS, NUMERICAL DATA, OXYGEN COMPOUNDS, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, RESEARCH PROGRAMS, THERMAL REACTORS, WATER, WATER COOLED REACTORS, WATER MODERATED REACTORS
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