scholarly journals The Shandong Shidao Bay 200 MW e High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM) Demonstration Power Plant: An Engineering and Technological Innovation

Engineering ◽  
2016 ◽  
Vol 2 (1) ◽  
pp. 112-118 ◽  
Author(s):  
Zuoyi Zhang ◽  
Yujie Dong ◽  
Fu Li ◽  
Zhengming Zhang ◽  
Haitao Wang ◽  
...  
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Technological Innovation ◽  
Pebble Bed ◽  
High Temperature Gas

scholarly journals Prediction calculations for the first criticality of the HTR-PM using the PANGU code

2021 ◽  
Vol 32 (9) ◽  
Author(s):  
Ding She ◽  
Bing Xia ◽  
Jiong Guo ◽  
Chun-Lin Wei ◽  
Jian Zhang ◽  
...  
Keyword(s):  
Monte Carlo ◽  
High Temperature ◽  
Power Plant ◽  
Uncertainty Analysis ◽  
Nuclear Data ◽  
High Fidelity ◽  
Pebble Bed ◽  
Input Model ◽  
High Temperature Reactor ◽  
High Temperature Gas

AbstractThe 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.

Verification of Alarm Displays for the Nuclear Power Plant With Two Modular High-Temperature Gas-Cooled Reactors

2018 ◽  
Author(s):  
Jia Qianqian ◽  
Guo Chao ◽  
Li Jianghai ◽  
Qu Ronghong
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Modular Design ◽  
Early Stage ◽  
Integrated System ◽  
Alarm System ◽  
Control Room ◽  
High Temperature Gas

The nuclear power plant with two modular high-temperature gas-cooled reactors (HTR-PM) is under construction now. The control room of HTR-PM is designed. This paper introduces the alarm displays in the control room, and describes some verification and validation (V&V) activities of the alarm system, especially verification for some new human factor issues of the alarm system in the two modular design. In HTR-PM, besides the regular V&V similar to other NPPs, the interference effect of the alarm rings of the two reactor modules at the same time, and the potential discomfort of the two reactor operators after shift between them are focused. Verifications at early stage of the two issues are carried on the verification platform of the control room before the integrated system validation (ISV), and all the human machine interfaces (HMIs) in the control room, including the alarm system are validated in ISV. The test results on the verification platform show that the alarm displays and rings can support the operators understand the alarm information without confusion of the two reactors, and the shift between the two reactor operators have no adverse impact on operation. The results in ISV also show that the alarm system can support the operators well.

scholarly journals The Design of Turbomachinery for the Gas Turbine (Direct Cycle) High Temperature Gas Cooled Reactor Power Plant

1977 ◽  
Author(s):  
R. G. Adams ◽  
F. H. Boenig
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Gas Turbine ◽  
Power Conversion ◽  
Reactor Power ◽  
Working Fluid ◽  
Primary Coolant ◽  
Reactor Power Plant ◽  
Direct Cycle ◽  
High Temperature Gas

The Gas Turbine HTGR, or “Direct Cycle” High-Temperature Gas-Cooled, Reactor power plant, uses a closed-cycle gas turbine directly in the primary coolant circuit of a helium-cooled high-temperature nuclear reactor. Previous papers have described configuration studies leading to the selection of reactor and power conversion loop layout, and the considerations affecting the design of the components of the power conversion loop. This paper discusses briefly the effects of the helium working fluid and the reactor cooling loop environment on the design requirements of the direct-cycle turbomachinery and describes the mechanical arrangement of a typical turbomachine for this application. The aerodynamic design is outlined, and the mechanical design is described in some detail, with particular emphasis on the bearings and seals for the turbomachine.

Steady-State Neutrbnic Investigations to the Accident of Water Ingress in Systems with Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel

1987 ◽  
Vol 97 (1) ◽  
pp. 72-88 ◽  
Author(s):  
F. Schürrer ◽  
W. Ninaus ◽  
K. Oswald ◽  
R. Rabitsch ◽  
Hj. Müller ◽  
...  
Keyword(s):  
Steady State ◽  
High Temperature ◽  
Reactor Fuel ◽  
Pebble Bed ◽  
Water Ingress ◽  
High Temperature Gas

scholarly journals A review of pebble flow study for pebble bed high temperature gas-cooled reactor

2019 ◽  
Vol 1 (3) ◽  
pp. 159-176 ◽  
Author(s):  
Shengyao Jiang ◽  
Jiyuan Tu ◽  
Xingtuan Yang ◽  
Nan Gui
Keyword(s):  
High Temperature ◽  
Pebble Bed ◽  
Pebble Flow ◽  
Flow Study ◽  
High Temperature Gas

Carbon materials in a high temperature gas-cooled reactor pebble-bed module

2018 ◽  
Vol 33 (2) ◽  
pp. 97-108 ◽  
Author(s):  
Xiang-wen Zhou ◽  
Yang Yang ◽  
Jing Song ◽  
Zhen-ming Lu ◽  
Jie Zhang ◽  
...  
Keyword(s):  
High Temperature ◽  
Carbon Materials ◽  
Pebble Bed ◽  
High Temperature Gas

Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors

2018 ◽  
Vol 4 (3) ◽  
Author(s):  
Yongyong Wu ◽  
Cheng Ren ◽  
Rui Li ◽  
Xingtuan Yang ◽  
Jiyuan Tu ◽  
...  
Keyword(s):  
High Temperature ◽  
Thermal Diffusivity ◽  
Inverse Method ◽  
Experimental Result ◽  
Test Facility ◽  
Inherent Safety ◽  
Pebble Bed ◽  
Effective Thermal Diffusivity ◽  
Under Construction ◽  
High Temperature Gas

The effective thermal diffusivity and conductivity of pebble bed in the high temperature gas-cooled reactor (HTGR) are two vital parameters to determine the operating temperature and power in varisized reactors with the restriction of inherent safety. A high-temperature heat transfer test facility and its inverse method for processing experimental data are presented in this work. The effective thermal diffusivity as well as conductivity of pebble bed will be measured at temperature up to 1600 °C in the under-construction facility with the full-scale in radius. The inverse method gives a global optimal relationship between thermal diffusivity and temperature through those thermocouple values in the pebble bed facility, and the conductivity is obtained by conversion from diffusivity. Furthermore, the robustness and uncertainty analyses are also set forth here to illustrate the validity of the algorithm and the corresponding experiment. A brief experimental result of preliminary low-temperature test is also presented in this work.

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