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Wu, Zongxin,Yu, Suyuan Korean Nuclear Society 2007 Nuclear Engineering and Technology Vol.39 No.2
The High Temperature Gas-cooled Reactor (HTGR) possesses inherent safety features and is recognized as a representative advanced nuclear system for the future. Based on the success of the HTR-10, the long-time operation test and safety demonstration tests were carried out. The long-time operation test verifies that the operation procedure and control method are appropriate for the HTR-10 and the safety demonstration test shows that the HTR-10 possesses inherent safety features with a great margin. Meanwhile, two new projects have been recently launched to further develop HTGR technology. One is a prototype modular plant, denoted as HTR-PM, to demonstrate the commercial capability of the HTGR power plant. The HTR-PM is designed as $2{\times}250$ MWt, pebble bed core with a steam turbine generator that serves as an energy conversion system. The other is a gas turbine generator system coupled with the HTR-10, denoted as HTR-10GT, built to demonstrate the feasibility of the HTGR gas turbine technology. The gas turbine generator system is designed in a single shaft configuration supported by active magnetic bearings (AMB). The HTR-10GT project is now in the stage of engineering design and component fabrication. R&D on the helium turbocompressor, a key component, and the key technology of AMB are in progress.
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Guo, Quanquan,Wang, Shaoxu,Chen, Shenggang,Sun, Yunlong Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.5
Safety analysis of nuclear power plant (NPP) especially in accident conditions is a basic and necessary issue for applications and commercialization of reactors. Many previous researches and development works have been conducted. However, most achievements focused on the safety reliability of primary pressure system vessels. Few literatures studied the structural safety of huge concrete structures surrounding primary pressure system, especially for the fourth generation NPP which allows existing of through cracks. In this paper, structural safety reliability of concrete structures of HTR-PM in accidental double-ended break of hot gas ducts was studied by Exceedance Probability Method. It was calculated by Monte Carlo approaches applying numerical simulations by Abaqus. Damage parameters were proposed and used to define the property of concrete, which can perfectly describe the crack state of concrete structures. Calculation results indicated that functional failure determined by deterministic safety analysis was decided by the crack resistance capability of containment buildings, whereas the bearing capacity of concrete structures possess a high safety margin. The failure probability of concrete structures during an accident of double-ended break of hot gas ducts will be 31.18%. Adding the consideration the contingency occurrence probability of the accident, probability of functional failure is sufficiently low.
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Peiyao Zhang,Quanquan Guo,Sen Pang,Yunlun Sun,Yan Chen 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.1
The high-temperature gas-cooled reactor pebble-bed module project is the first commercial Generation-IV NPP(Nuclear Power Plant) in China. A new joint is used for the vertical support of RPV(ReactorPressure Vessel). The steel corbel is integrally embedded into the reactor-cabin wall through eightasymmetrically arranged pre-stressed high-strength bolts, achieving the different path transmission ofshear force and moment. The vertical monotonic loading test of two specimens is conducted. The resultsshow that the failure mode of the joint is bolt fracture. There is no prominent yield stage in the wholeloading process. The stress of bolts is linearly distributed along the height of corbel at initial loading. Asthe load increases, the height of neutral axis of bolts gradually decreases. The upper and lower edges ofthe wall opening contact the corbel plate to restrict the rotation of the corbel. During the loading, thepre-stress of some bolts decreases. The increase of the pre-stress strength ratio of bolts has no noticeableeffect on the structure stiffness, but it reduces the ultimate bearing capacity of the joint. A simplifiedcalculation model for the elastic stage of the joint is established, and the estimation results are in goodagreement with the experimental results
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