Verification of SPACE Capability using Plant Test Data

The Safety and Performance Analysis Code 3.0 (SPACE 3.0) which is a best-estimate thermal-hydraulic analysis code for nuclear power plants has been licensed for safety analyses in 2017. During the development period, a comprehensive code capability assessment has been performed against a numerous conceptual problems and experimental data. As the final assessment stage, the thermal-hydraulic behaviors of the operating power plant are analyzed to verify the best-estimate capability of the SPACE code. Two test cases performed during the Shinkori unit 3 Power Ascension Test (PAT) period were selected; the turbine load rejection to house load test and the turbine trip and Natural Circulation Cooldown (NCC) test. In order to analyze these test cases, the as-built the plant control system models are developed using the SPACE input model. Finally, the code predictions are directly compared with the measured test data, and the verification results are presented in this paper.