Session: 05-04: Nuclear Engineering and Safety Analysis
Paper Number: 133789
133789 - Construction and Exploration of a Diagnostic Platform for High-Temperature Gas-Cooled Reactor Units
Abstract:
Abstract: High Temperature Gas-cooled Reactor is internationally recognized as an advanced type of reactor with excellent safety. Its short construction period, high power generation efficiency, and simple system make it a focus of world nuclear energy development. With the continuous growth of energy demand and the improvement of environmental awareness, nuclear energy as a clean and efficient energy source has attracted much attention. As an advanced nuclear power generation technology, High Temperature Gas-cooled Reactor plays an important role in the energy field due to their high thermal efficiency and low carbon emissions. Ensuring their safe and stable operation is crucial for the sustainability of energy supply. However, during the operation of High Temperature Gas-cooled Reactor, various challenges and faults may be encountered. Therefore, establishing a reliable unit diagnosis platform is of great significance for ensuring the smooth operation of High Temperature Gas-cooled Reactors. At present, the most widely used and mature diagnostic software on the market is about pressurized water reactor, while there is relatively little research on diagnostic software for High Temperature Gas-cooled Reactors. This article takes the 10 MW High Temperature Gas-cooled Reactor Test Module (HTR-10) as an example to develop and establish a diagnostic platform for High Temperature Gas-cooled Reactor units. This platform integrates functions such as data collection and processing module, feature extraction and selection module, fault recognition and classification module, prediction and analysis module, etc. The platform collected a total of 192 key monitoring points of various equipment during the operation of HTR-10, including temperature, pressure, flow rate, and valve switch status. At the same time, Bayesian network modeling was used to model the corresponding accidents by inputting information from key monitoring points, The transmission and inference in the Bayesian model are implemented to obtain the diagnostic results of the unit status at that moment, which are presented in the form of the probability of corresponding accidents. Real time online comprehensive monitoring and analysis of the operating status of High Temperature Gas-cooled Reactor are achieved, providing comprehensive support for the operation and maintenance of High Temperature Gas-cooled Reactors. The article first reviews the background and development of High Temperature Gas-cooled Reactor technology, and then discusses in detail the architecture design, key technologies, and practical application effects of the diagnostic platform. Through the development and application of this platform, operators can monitor the status of High Temperature Gas-cooled Reactors in real time, accurately predict potential faults, and ensure their safe and efficient operation.
Presenting Author: cui Mao Tsinghua university
Presenting Author Biography: Mao Cui, female, majoring in Nuclear Science and Technology, is an engineer currently employed at the Institute of Nuclear Energy and New Energy Technology, Tsinghua University. The main research direction is to simulate detector calculations using Monte Carlo methods (GEANT4, MCNP and other software), and to develop anti Compton based on anti coincidence measurement technology. In addition, it also involves the development of software for oil logging, radioactive nuclide analysis, radiation protection, accident consequence assessment, and the construction of nuclear emergency platforms.
Authors:
cui Mao Tsinghua universityHaisheng Liu Tsinghua University
Di Geng Tsinghua University
Yuhua Liu Tsinghua University
Zaizhe Yin Tsinghua University
Construction and Exploration of a Diagnostic Platform for High-Temperature Gas-Cooled Reactor Units
Submission Type
Technical Paper Publication