Abstract As one of the safety demonstration tests performed on the 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10), a control rod withdrawal (CRW) test was conducted without reactor scram. In the test process, about 5‰ ∆k/k positive reactivity was introduced into the core at 30% rated power. In this study, the CRW test is simulated using the THERMIX code and the analysis result is compared with the test data. The code reproduces the reactor power well except some discrepancies in predicting the first peak power after the recriticality. Thus, the basic simulation capability of THERMIX can be verified. Besides, the temperature coefficient of reactivity (TCR), the residual heat level (RHL) and the xenon poisoning effect (XPE) are considered as the more crucial aspects affecting the THERMIX simulation accuracy. Therefore, sensitivity studies are performed based on the assumed changes of TCR, RHL and XPE with the objective of guiding further efforts in improving the accuracy of the future post-test simulations.
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