Target Reactor
SMR
APR-1400
MSR
VHTR
Space Reactor
SMART
i-SMR
Design
Nuclear Core Design
Shielding Design
Fuel Performance
T/H Coupling
Small Modular Reactor, SMR (소형모듈형원자로)
The term SMR refers to small and medium-sized reactors with a capacity of 600 MWe or less, collectively encompassing small and medium-sized nuclear reactors.
1985, IAEA (TECDOC-347) : SMPR (Small and Medium Power Reactor)
1991, OECD : Small and Medium Reactor (SMR) < 600 Mwe
1996, IAEA (TECDOC-881) : SMR (Small and Medium Reactor) ~ 700 Mwe
Features of SMR
Simpler design, Increased safety margin,
Better match to grid requirement,
Open up energy markets,
Easier multi-unit siting,
Lower financial risk.
SMR Chelleanges
(Unresolved Issues) In the 1991 OECD report, issues and areas for improvement related to SMR development were highlighted, including Economic Competitiveness and Lack of any Operating Plants.
(Economy of Scale) The specific capital cost ($/kWe) of a nuclear reactor is inversely proportional to its size, ranging from -0.6 to -0.3. The numerator value (cost) remains constant, suggesting an increase in the denominator. Project investment constitutes 66%, Operation and Maintenance 16%, and Fuel and Wastes 17% of the overall cost structure.The Monte Carlo method has advantage and disadvantage. In the particle transport analysis, the MC method can handle continuous energy cross section library and treat the complex geometric information directly without some approximations. To overcome the disadvantage of the MC method, we need some improvements. In the other words, it needs challenges.
(Economic Paradigm Shift) Is there economic viability for SMRs?
Multiple unit construction
Learning curve (standardization)
Short construction period
Provide consumer-appropriate capacity (generate demand)
Design innovation (simplification, standardization, factory construction)
Researches and Studies on SMR
Our researches and studies though last 5 years covers those SMR challeges.
Multi-physics and Feedback Calculation : "BEAVRS benchmark analysis by DeCART stand-alone calculations and comparison with DeCART/MATRA multi-physics coupling calculations"
Advanced Uncertainty Analyses for Safety Analyses with Advanced method :
(1) "McCARD/MIG Stochastic sampling calculations for nuclear cross section sensitivity and uncertainty analysis",
(2) "Establishment of DeCART/MIG stochastic sampling code system and Application to UAM and BEAVRS benchmarks"
High-fidelity Burnup Analysis :
"Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD"
New Evalauted Nuclear Data and its Application to New Core Design :
(1) "Comparison of ENDF/B-VIII.0 and ENDF/B-VII.1 in criticality, depletion benchmark, and uncertainty analyses by McCARD",
(2) "McCARD Criticality Benchmark Analyses with Various Evaluated Nuclear Data Libraries"
Improvement of Lattice Code Library :
"An imporvement DeCART library generation procedue with explicit resonance interference using continous energy Monte Carlo calculation"