Application of Adjoint Sensitivity Analysis Procedure to Single Phase Thermal-Hydraulics with Heat Structure Code Author 김민길, 이정익 Conference 2018 한국원자력학회 추계학술발표회 Date 20181025 본문 이전글Development Status and Validation of Nuclear System Analysis Code Using Higher-order Numerical Scheme and Moving Mesh Method 다음글Preliminary study of thermal energy storage integration with nuclear power plant for flexible operation 검색 목록