scholarly journals The Implementation of Diverse Actuation System in ACPR1000 Nuclear Power Plants

2021 ◽  
Vol 2021 ◽  
pp. 1-10
Author(s):  
Zhen-Ying Wang ◽  
Zhi-Yun Liu ◽  
Ting-Wei Ma ◽  
Chen Sun ◽  
Liu Liu ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Point Of View ◽  
Sensors And Actuators ◽  
Independent Verification ◽  
Actuation System ◽  
Field Programmable ◽  
Technical Issues ◽  
The Impact

In order to improve the capability of dealing with software common cause failure (CCF) of digital reactor protection and monitoring system (RPMS), the diverse actuation system (DAS) is introduced for ACPR1000 nuclear power plants. From economic and feasibility point of view, the solution of DAS sharing with RPMS sensors and actuators is suggested; after capturing the function requirement of DAS, the automatic functions and manual functions assigned to it are determined based on transient analysis of design basic accidents concurrent with software CCF of RPMS. The independent verification proves that the reactor can be fallen back to and maintained at safety shutdown state, thanks to these DAS functions. Insight into probabilistic safety assessment proves significant reductions of risks are contributed. The critical technical issues while implementing DAS, such as measures to ensure its diversity from RPMS, precautions for preventing from its spurious actuation, isolation and independency from RPMS, and its testability and maintainability, are deliberately settled to improve its engineering reliability and alleviate the impact on RPMS as far as possible. Field programmable gate array technology that is diversified from RPMS is chosen to build DAS of ACPR1000 nuclear power plant, and the commissioning test verifies that it is capable of performing its designed functions. At last, a set of DAS-specific, paper-based, and event-oriented emergency operating procedure is developed, verified, and validated. Until now, the DAS system has always been successfully operating in all ACPR1000 nuclear power plants for several years.

scholarly journals Comparison and Evaluation of Domestic and Foreign Radiation Environmental Standards for Nuclear Power Plants

2021 ◽  
Vol 2083 (2) ◽  
pp. 022020
Author(s):  
Jiahuan Yu ◽  
Xiaofeng Zhang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
The United States ◽  
Discharge System ◽  
Radioactive Effluent ◽  
Effluent Discharge ◽  
The Impact

Abstract With the development of the nuclear energy industry and the increasing demand for environmental protection, the impact of nuclear power plant radiation on the environment has gradually entered the public view. This article combs the nuclear power plant radiation environmental management systems of several countries, takes the domestic and foreign management of radioactive effluent discharge from nuclear power plants as a starting point, analyses and compares the laws and standards related to radioactive effluents from nuclear power plants in France, the United States, China, and South Korea. In this paper, the management improvement of radioactive effluent discharge system of Chinese nuclear power plants has been discussed.

The Impact of Nuclear Power Plants on the Cooling Pond

2021 ◽  
pp. 309-314
Author(s):  
Irma Martyn ◽  
Yaroslav Petrov ◽  
Sergey Stepanov ◽  
Artem Sidorenko
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Cooling Pond ◽  
The Impact

Study on the Impact Limiter Design in Spent Fuel Transfer Cask in Nuclear Power Plants

2020 ◽  
Author(s):  
Yuchen Hao ◽  
Yue Li ◽  
Jinhua Wang ◽  
Bin Wu ◽  
Haitao Wang
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Theoretical Method ◽  
Structure Design ◽  
Design Approach ◽  
Spent Fuel ◽  
Typical Structure ◽  
Explicit Finite Element ◽  
The Impact

Abstract In nuclear power plants, the amount of spent fuel stored on-site is limited. Therefore, it is necessary to be shipped to off-site storage or disposal facilities regularly. The key risk in the transfer of spent fuel involves a release of radiation that could cause harmful effects to people and the environment. Transfer casks with impact limiters on both ends are always employed to ensure safe containment of radioactive materials, which should be verified by the 9 meters drop test onto an unyielding surface according to IAEA SSR-6. In this paper, we focus on the influence of the impact-limiter parameters, including geometry dimensions and mechanical properties, on the results of drop events to achieve an optimized approach for design. The typical structure of impact limiter is bulk energy-absorbed material wrapped by thin stainless-steel shells. Compared to traditional wood, foam has advantages of isotropy and steady quality. In this paper, theoretical and numerical methods are both adopted to investigate the influence of impact limiters during hypothetical accidental conditions for optimizing buffer influence and protecting the internal fuel components. First of all, a series of polyurethane foam is selected according to the theoretical method, because its mechanical property is related to density. Therefore, using explicit finite element method to investigate the influence of parameters of foam in impact limiter. These discrete points from the above result can be utilized to establish damage curves by date fitting. Finally, a design approach for spent fuel transfer cask is summarized, to provide a convenient formula to predict the damage and optimize structure design in drop condition. Furthermore, this design approach can be applied in the multi-module shared system of SNF, which can contain different fuel assemblies.

scholarly journals Analysis of Factors Affecting Thermodynamic Efficiency in Generation III+ PWR Nuclear Power Plants.

2017 ◽  
Vol 4 ◽  
pp. 141-154
Author(s):  
Marcus Vitlin ◽  
Miroshan Naicker ◽  
Augustine Frederick Gardner
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Rankine Cycle ◽  
Steam Temperature ◽  
Factors Affecting ◽  
Electrical Efficiency ◽  
Balance Of Plant ◽  
The Impact ◽  
The Relationship

Generation III+ reactors are the latest generation of Nuclear Power Plants to enter the market. The key evolution in these reactors is the introduction of stringent safety standards. This is done through thorough incident scenario analysis and preparation, resulting in the addition of novel active and passive auxiliary safety systems, affecting the power consumption in the balance of plant. This paper analyses the parameters of PWR power plants of similar design, to determine the parameters for optimal efficiency, regarding gross and net electrical output, determining the impact the balance of plant has on this efficiency. While two of the three main factors affecting the Rankine cycle – boiler pressure and steam temperature – behaved as theoretically expected, there was a notable point of departure with the third parameter – condenser pressure. The relationship between steam temperature and gross electrical efficiency was linear across all reactors but the relation between the steam temperature and the net electrical efficiency ceased to be linear for secondary loop steam temperatures above 290°C. The relationship between boiler pressure and both gross and net electrical efficiency was linear, proving the Rankine cycle. A relationship was not observed between the condenser pressure and either the gross or net electrical efficiency

The impact of non-optimized operation of nuclear power plants on the nuclear fuel burn-up

Kerntechnik ◽  
2004 ◽  
Vol 69 (3) ◽  
pp. 84-87
Author(s):  
H. R. V. de Oliveira ◽  
A. S. Martinez
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Fuel Burn ◽  
The Impact

Study on the Nonradioactive Environmental Impact Assessments for Chinese Nuclear Power Plants

2013 ◽  
Author(s):  
Xinyu Wei ◽  
Hongbin Ma ◽  
Xiaowei Xiong ◽  
Duanjie Yang ◽  
Zhaorong Shang
Keyword(s):  
Environmental Impact ◽  
Impact Assessment ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Environment Impact ◽  
Environmental Impact Assessments ◽  
Environment Impact Assessment ◽  
The Social ◽  
The Impact

In China, the radioactive environmental impact assessment (EIA) for nuclear power plants (NPPs) had been carried out in detail due to the specific characteristic of radiation and the social universal attention. However, the nonradioactive environment impact assessment for NPP doesn’t get enough attention. This should be improved, since the operation of NPPs could cause some serious nonradioactive environment impacts. Based on the investigation of EIA for American NPPs, the following suggestions were put forward for Chinese EIA: (1) the laws and regulations in China need to be revised for the EIA of NPPs; (2) the statistics of chemicals or biocides used in the operation of NPPs and their discharged concentration need to be tested; (3) the impact assessments of nonradioactive gas emissions as well as hazardous wastes need to be carried out to meet the national requirements; and (4) the monitoring of nonradioactive waste also needs to be carried out for NPPs to obtain the basic data.

French Nuclear Power Plants Life Management Ageing Management Process: Matrix of Degradation Evaluation for Strategic Decision Combined With Components

2005 ◽  
Author(s):  
Georges Bezdikian
Keyword(s):  
Asset Management ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Point Of View ◽  
Strategic Decision ◽  
Life Management ◽  
Life Evaluation ◽  
Maintenance Program ◽  
Periodic Maintenance

The life management of French Nuclear Power Plants is an important issue and a major stake considering the aging management assessment of the key components of the plant, both from an economic and a technical point of view. The actual life evaluation is: • The first 3-loop PWR plants have 25 years in operation, • The first 4-loop PWR plants have 19 years in operation. To optimize the best and strategic choice in order to achieve the best possible performance and to prepare the technical and economical choice and decision considering: • the mode of degradation for different components, • the industrial capacity and capability to replace or to repair components, • the life evaluation of components with time limit in operation, the French utility has organized the life management of Nuclear Plant in function of several program of knowledge on degradation mode from the large and long term experience feedback and the maintenance program for life management based on normal and periodic maintenance actions and exceptional maintenance carried out on strategic components. This paper shows the table of degradation mode and different actions engaged by utility on: • In-Service Inspection, periodic maintenance, • Alternative maintenance actions, • Exceptional program of maintenance based on several mitigation and strategic replacement of components. This paper provides the reader with an overview of how advanced information processing techniques to the improvement of in-service inspections, condition-based maintenance, and asset management.

PR as a tool for the development of nuclear energy in Russia and abroad

2020 ◽  
Vol 13 (2) ◽  
pp. 128-135
Author(s):  
X. V. Mishchenko ◽  
A. E. Uzhanov
Keyword(s):  
Decision Making ◽  
Public Opinion ◽  
Public Relations ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Energy ◽  
Nuclear Power Plants ◽  
Nuclear Industry ◽  
Foreign Countries ◽  
The Impact

The author estimates the impact of PR technologies on the development of nuclear power in Russia and in a number of foreign countries (USA, China, Japan, France). It is determined that as soon as at the stage of development of nuclear generation projects and other nuclear industry facilities, the use of public relations (PR), with a targeted impact on public opinion and interaction with target audiences (TA) at its core, has a significant impact on decision-making in favor of the construction of nuclear power plants, minimizes the protest behavior of the population. It is shown that the advantages of nuclear power among alternative energy sources for strengthening the socio-economic potential of states and increasing their environmental well-being are most clearly, quickly and effectively disclosed through using public relations tools. PR enables to form an adequate and correct understanding of the physical and chemical foundations of nuclear power engineering, the main threats and systems for their minimization or complete elimination at the conceptual, socio-psychological and socio-logical levels, as well as to form, in terms of specific objects and tools, the technological and organizational facilities for the development of nuclear energy projects both in Russia and in foreign countries. The activities of foreign and Russian companies aimed at ensuring loyal public opinion in relation to nuclear projects are critically described and analytically compared. The chronological framework covers the recent period: from the beginning of the 2000s to 2020. This period is noted as the most significant for the development of nuclear power in the world. Statistical data on changes in the attitude of the public in different countries to the prospects for the development of nuclear energy after the Chernobyl and Fukushima-1 disasters are presented. It is concluded that it is PR in its integrated application that contributes to government decision-making and public support in the construction of nuclear power plants in Russia and abroad.

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