Abstract
The high-temperature reactor pebble-bed module (HTR-PM) is a modular high-temperature gas-cooled reactor demonstration power plant. Its first criticality experiment is scheduled for the latter half of 2021. Before performing the first criticality experiment, a prediction calculation was performed using PANGU code. This paper presents the calculation details for predicting the HTR-PM first criticality using PANGU, including the input model and parameters, numerical results, and uncertainty analysis. The accuracy of the PANGU code was demonstrated by comparing it with the high-fidelity Monte Carlo solution, using the same input configurations. It should be noted that keff can be significantly affected by uncertainties in nuclear data and certain input parameters, making the criticality calculation challenge. Finally, the PANGU is used to predict the critical loading height of the HTR-PM first criticality under design conditions, which will be evaluated in the upcoming experiment later this year.
Highlights
The high-temperature reactor pebble-bed module (HTRPM) [1] is the world’s first 200 MWe modular pebble-bed high-temperature gas-cooled reactor (HTGR) in a demonstration power plant with the safety features of fourthgeneration nuclear energy systems
This paper presents the calculation details for predicting the high-temperature reactor pebble-bed module (HTR-PM) first criticality using PANGU, including the input model and parameters, numerical results, and uncertainty analysis
The result predicted by Institute of Nuclear and New Energy Technology (INET) was reportedly very close to the experimental result [4], the overall benchmark exercise yielded a deviation of ± 4% in the effective multiplication factor, which indicates that reactor physics analysis in pebble-bed HTGRs is far from a well-established art [5]
Summary
The high-temperature reactor pebble-bed module (HTRPM) [1] is the world’s first 200 MWe modular pebble-bed high-temperature gas-cooled reactor (HTGR) in a demonstration power plant with the safety features of fourthgeneration nuclear energy systems. It was designed by the Institute of Nuclear and New Energy Technology (INET), Tsinghua University, based on technologies and experiences obtained from the 10 MW high-temperature gascooled test reactor (HTR-10) [2]. Since the HTR-PM is a scaled-up and developed version of the HTR10, it has particular value for reactor physics analysis in large commercial pebble-bed HTGRs
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