Abstract
The 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) is the first High Temperature Gas-cooled Reactor (HTGR) in China, which was operated from January 2003 to May 2007. The HTR-10 operation history provides very important data for the validation of HTGR codes. In this paper, the HTR-10 operation history is simulated with the PANGU code, which has been recently developed for HTGR reactor physics analysis and design. Models and parameters are constructed based on the measured data of the actual conditions. The simulation results agree well with the measurements in all steady-state power periods. The discrepancy of keff is generally below 0.5%, and the discrepancy of coolant outlet temperature is generally below 5°C. It is also figured out that the burnup of graphite impurities has considerable influence on the keff at the end of the operation history, which can cause over 1.5% discrepancy when neglecting the burnup of graphite impurities. By this work, the PANGU code’s applicability in actual HTGR fuel cycle simulations is demonstrated.
Highlights
The 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) Wu et al (2002), designed, constructed, and operated by Institute of Nuclear and New Energy Technology (INET), Tsinghua University, and is the first High Temperature Gas-cooled Reactor (HTGR) in China
In order to analyze the influence caused by the burnup of the equivalent boron content (EBC), comparison simulations are done by changing the burnable ratio to 0 and 100%, respectively
It is figured that the burnable ratio of EBC has significant influence on the HTGR fuel cycle calculation
Summary
Following the IC state, mixing pebbles were gradually added into the core, FIGURE 3 | Control rod position (averaged) during the operation history. The first-category data is the measured control rod position in each power period, as PARAMETERS AND MODELS USED IN THE SIMULATION. Because PANGU employs a 2D R-Z model for whole core criticality calculations, it uses an averaged control rod position in each power period, which is calculated from the measured data. In. the first stages of the HTR-10 operation history, i.e. from the initial core to the full core state, mixing pebbles were loaded and the core height increased along with the reactor operation. The following pebble flow model is employed in PANGU to simulate the HTR-10 fuel loading and recycling procedures.
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