scholarly journals Research on Evolution Path of Innovation Chain of Nuclear Power Industry-based on Innovation Synergy

Author(s):  
Yu-qiong LI ◽  
Bei-bei ZHAO ◽  
Yang LI ◽  
Yuan YAN ◽  
Xiao-long FU ◽  
...  
2020 ◽  
Vol 2020 ◽  
pp. 1-9
Author(s):  
Hongyun Xie ◽  
Haixia Gu ◽  
Chao Lu ◽  
Jialin Ping

Real-time Simulation (RTS) has long been used in the nuclear power industry for operator training and engineering purposes. And, online simulation (OLS) is based on RTS and with connection to the plant information system to acquire the measurement data in real time for calibrating the simulation models and following plant operation, for the purpose of analyzing plant events and providing indicative signs of malfunctioning. OLS has been applied in certain industries to improve safety and efficiency. However, it is new to the nuclear power industry. A research project was initiated to implement OLS to assist operators in certain critical nuclear power plant (NPP) operations to avoid faulty conditions. OLS models were developed to simulate the reactor core physics and reactor/steam generator thermal hydraulics in real time, with boundary conditions acquired from plant information system, synchronized in real time. The OLS models then were running in parallel with recorded plant events to validate the models, and the results are presented.


Author(s):  
Xuanxuan Shui ◽  
Yichun Wu ◽  
Junyi Zhou ◽  
Yuanfeng Cai

Field programmable gate arrays (FPGAs) have drawn wide attention from nuclear power industry for digital instrument and control applications (DI&C), because it’s much easier and simpler than microprocessor-based applications, which makes it more reliable. FPGAs can also enhance safety margins of the plant with potential possibility for power upgrading at normal operation. For these reasons, more and more nuclear power corporations and research institutes are treating FPGA-based protection system as a technical alternative. As nuclear power industry requires high reliability and safety for DI&C Systems, the development method and process should be fully verified and validated. For this reason, to improve the application of FPGA in NPP I&C system, the specific test methods are critical for the developers and regulators. However, current international standards and research reports, like IEC 62566 and NUREG/CR-7006, which have demonstrated the life circle of the development of FPGA-based safety critical DI&C in NPPs, but the specific test requirements and methods which are significant to the developers are not provided. In this paper, the whole test process of a pressurized water reactor (PWR) protection sub-system (Primary Coolant Flow Low Protection, Over Temperature Delta T Protection, Over Power Delta T Protection) is described, including detail component and integration tests. The Universal Verification Methodology (UVM) based on System Verilog class libraries is applied to establish the verification test platform. All these tests are conducted in a simulation environment. The test process is driven by the test coverage which includes code coverages (i.e., Statement, Branch, Condition and Expression, Toggle, Finite State Machine) and function coverage. Specifically, Register Transaction Level (RTL) simulation is conducted for Component tests, while RTL simulation, Gate Level simulation, Timing simulation and Static timing analysis are conducted for the integration test. The issues (e.g., the floating point calculation, FPGA resource allocation and optimization) arose in the test process are also analyzed and discussed, which can be references for the developers in this area. The component and integration tests are part of the Verification and Validation (V&V) work, which should be done by the V&V team separated from the development team. The testing method could assure the test results reliable and authentic. It is practical and useful for the development and V&V of FPGA-based safety DI&C systems.


World Pumps ◽  
2016 ◽  
Vol 2016 (3) ◽  
pp. 28-30 ◽  
Author(s):  
Colin Elcoate

Author(s):  
V. A. Lazarenko

The article presents the analysis of the influence of historical factors on the development of Russian cities of nuclear power industry and the genetic types of these cities. Most of these cities are young, their socioeconomic state depends on the city-forming enterprise. The formation and development of nuclear power plant (NPPs) cities went in two ways: the city was built in parallel with the nuclear power plant (e.g., Novovoronezh, Desnogorsk, Kurchatov); the NPP was built near the settlement, and then NPP has influenced on socioeconomic development of the settlement, its employment structure, etc. (Volgodonsk and Balakovo). In USSR/Russia practice, the first way dominated, when an urban-type settlement was built near a NPP, such settlement then intensively grew and developed into a city. There are three types of Russian cities with NPPs: the cities formed and developed before the construction of the NPP; the cities developed due to the operation of NPPs, and the cities created and developed due to the operation of NPPs. It was found that the factor of formation of nuclear power industry in the city is decisive in the social development of almost all cities of NPPs and affects their current state.


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