Analysis of the HTGR Proliferation Resistance

2008 ◽  
Author(s):  
Vitaly V. Petrunin ◽  
Nikolay G. Kodochigov ◽  
Yury P. Sukharev ◽  
Sergey L. Osipov ◽  
Elena V. Marova
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Nuclear Material ◽  
Nuclear Power Engineering ◽  
Power Engineering ◽  
Nuclear Technology

Increased interest in development of nuclear power engineering, first of all in non-nuclear countries, puts an emphasis on the designing of small and medium nuclear power plants and determines the growth in nuclear technology export from countries with advanced nuclear industries. It accentuates the issue of reduction of the nuclear material proliferation risk, which was repeatedly raised on the national an international levels (materials of INPRO, GNEP, IAEA).

scholarly journals Current State of Safety of the Nuclear Power Plants, Prospect of the Development of Nuclear Power Engineering and Conceptual Issues of Development Strategy of Environmentally Friendly Nuclear Power

10.12737/4944 ◽  
2014 ◽  
Vol 3 (3) ◽  
pp. 60-73 ◽  
Author(s):  
Хвостова ◽  
Marina Khvostova ◽  
Острецов ◽  
Igor Ostretsov ◽  
Кузнецов ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Spent Nuclear Fuel ◽  
Environmentally Friendly ◽  
Nuclear Power Engineering ◽  
Power Engineering ◽  
Stress Tests ◽  
Current State

The article considers current state of safety of nuclear power engineering. It presents a brief summary of stress-tests at nuclear power plants in the European Union and Russia. It reveals that the power on breeders shall not develop due to its low efficiency, high expenses and the risk of propagation of nuclear materials. Moreover, construction of plutonium processing production operations on nuclear power plant platforms with breeders, production of mixed uranium-plutonium nuclear fuel and synthesis ofamericium-241 in the spent nuclear fuel calls ecological safety into question. The article also addresses conceptual issues of creation of environmentally friendly nuclear power on the basis of nuclear relativistic technology. It is shown that such power shall not produce "bomb" materials and, therefore, will find extensive application around the world. Thereby the most challenging international problems of the present will be solved. The new nuclear power can become a basis for hydrogen production, which might solve practically all problems of mankind, including even food, by means of nuclear energy.

scholarly journals Methods of Accounting Aging of the Main Equipment of Nuclear Power Plants Using the Example of the Control System for the Installation of AM

2018 ◽  
Vol 3 (3) ◽  
pp. 452
Author(s):  
Bychok A.S ◽  
Mukhin V.Yu. ◽  
Samokhin D.S
Keyword(s):  
Control System ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Nuclear Technology ◽  
Urgent Problem ◽  
Main Equipment ◽  
Functional Reliability ◽  
Resource Characteristics

Accounting for the aging of equipment and analysis of resource characteristics of nuclear technology facilities is an urgent problem. In this paper, we show methods of solving for finding functional reliability. The analysis of the functional reliability of the most important control and protection control (SCP) systems of the AM-1 installation was also carried out

Renaissance der Atomkraft? Vermutlich nicht!

2009 ◽  
Vol 39 (156) ◽  
pp. 425-440 ◽  
Author(s):  
Lutz Mez ◽  
Mycle Schneider
Keyword(s):  
Global Warming ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Raw Materials ◽  
Financial Sector ◽  
Nuclear Industry ◽  
Nuclear Technology ◽  
Skilled Worker

The international nuclear lobby is constantly talking about a nuclear renaissance. But nuclear power is rather in the dusk than in the dawn. Missing industrial capacities, skyrocketing costs for raw materials and new nuclear power plants, the dramatic skilled worker/manager shortage and a sceptical financial sector are the main problems of nuclear industry. And nuclear technology as saviour against global warming is no good either.

Research and Application Status of the Modular Technology in Nuclear Power Engineering of CGNPC

2013 ◽  
Author(s):  
Qinwu Lu
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Modular Design ◽  
National Level ◽  
Nuclear Power Engineering ◽  
Power Engineering ◽  
Design System ◽  
Modular Construction ◽  
Modular Technology ◽  
Design And Construction

Modular design and construction is one of the distinctive features of the 3rd generation nuclear power technology. In order to promote the technological innovations in nuclear power engineering design and construction and develop the self-owned modular technology, China Guangdong Nuclear Power Holding Co., Ltd (hereafter referred as to CGNPC) has carried out the R&D and application of the modular technology based on the CPR1000-type nuclear power plants, and has made the national-level achievements in the establishment of modular design technology system, development of 3D modular design system and application of modular construction of containment steel liner in the demonstration projects.

scholarly journals Belarus Power Engineering System Modeling Taking into Account the Nuclear Power Plant Commissioning

2021 ◽  
Vol 64 (1) ◽  
pp. 5-14
Author(s):  
A. A. Mikhalevic ◽  
U. A. Rak
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Energy Systems ◽  
Operating Conditions ◽  
Power Engineering ◽  
Power Balance ◽  
Engineering System ◽  
Large Share ◽  
Load Duration

The article presents the analysis of the specific features of modeling the operation of energy systems with a large share of nuclear power plants (NPP). The study of operating conditions and characteristics of different power units showed that a power engineering system with a large share of NPP and CHPP requires more detailed modeling of operating modes of generating equipment. Besides, with an increase in the share of installations using renewable energy sources, these requirements are becoming tougher. A review of the literature revealed that most often the curve of the load duration and its distribution between blocks are used for modeling energy systems. However, since this method does not reflect a chronological sequence, it can only be used if there are no difficulties with ensuring power balance. Along with this, when the share of CHP and nuclear power plants is high, to maintain a balance of power one must know the parameters and a set of powered equipment not only currently but, also, in the previous period. But this is impossible if a curve of load duration is used. For modeling, it is necessary to use an hourly load curve and to calculate the state of the energy system for each subsequent hour in chronological order. In the course of a comparative analysis of available computer programs, it was not possible to identify a suitable model among the existing ones. The article presents a mathematical model developed by the authors, which makes us possible to simulate the operation of a power engineering system with a large share of NPP and CHPP while maintaining the power balance for each hour of the forecast period. Verification of the proposed model showed good accuracy of the methods used.

scholarly journals Generation IV supercritical water-cooled nuclear reactors: Realistic prospects and research program

2019 ◽  
Vol 5 (1) ◽  
pp. 67-74 ◽  
Author(s):  
Pavel L. Kirillov ◽  
Galina P. Bogoslovskaya
Keyword(s):  
Supercritical Water ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Thermal Power ◽  
Operating Experience ◽  
Supercritical Pressure ◽  
Power Engineering ◽  
Fourth Generation ◽  
Supercritical Water Cooled Reactor

Existing conditions make possible obtaining information that being discussed openly by wide scientific community could help outlining or even establishing the expediency of a particular area of present and future research. Use link http://www.sciencedirect.com to learn about the topics or areas that most attract researchers from different countries. The Generation IV International Forum (GIF-IV) established in January 2000 has set a goal to improve the new generation of nuclear technologies in the following areas: stability, safety and reliability, economic competitiveness, proliferation resistance and physical protection. The purpose of the present publication is to prepare a discussion of one of the directions of development of fourth-generation NPPs, the groundwork for which has already been laid in thermal power engineering in various countries. The number of papers published annually on this topic is the largest among other similar topics dedicated to nuclear power plants of the fourth generation. Judging from the operating experience of existing nuclear power plants using water as a coolant, it can be ascertained that the tendency of building water-cooled nuclear power plants will remain during the next 30 to 50 years. During the present stage the task in the development of alternative types of reactors will be limited to demonstration of their performance and acceptability for future power engineering and the society. The project of supercritical water-cooled reactor is based on the operating experience of VVER, PWR, BWR reactors (more than 14,000 reactor-years); many years of experience accumulated in operating fossil thermal power plants (more than 400 power units; 20,000 years of operation of power units) using supercritical (25 MPa, 540°C) and super-supercritical (35–37 MPa, 620–700°C) water steam. In Russia more than 140 supercritical pressure units are currently in operation. Numerical calculation and design of supercritical water-cooled reactor (similarly to BR-10 reactor) will allow not only training personnel for future development of this technology, but will also help revealing the most difficult points requiring experimental confirmation with application of independent test facilities, as well as formulating the plan of first priority experimental studies. Knowledge accumulated over the last 10 years in the world allows the following: further specifying the already developed concept; developing a plan of specific priority studies; compiling task order for designing small-power pilot VVER SKP-30 reactor (30 MW-th). The scope of problems that are to be solved to substantiate VVER-SCP reactor and commence designing an experimental reactor with thermal capacity of 30 MW is the same as that in developing any type of nuclear reactor: physics of the reactor core; material related matters (primarily concerned with the reactor pressure vessel, fuel, and fuel rod cladding); thermal hydraulics of rod bundles in the near- and supercritical areas; water chemistry at supercritical pressure; corrosion of materials, development of safety systems. Research must be carried out both in static conditions and under irradiation. The absence in Russia during the extended time period of approved program with allocation of appropriate funding and preservation of the existing status during the coming two or three years will lead to the situation when Russia will be hopelessly lagging behind in the development of SCWR technology.

Updated Knowledge Implemented to the Revision of Environmental Fatigue Evaluation Method for Nuclear Power Plant in JSME Code

2009 ◽  
Author(s):  
Makoto Higuchi ◽  
Takao Nakamura ◽  
Yasuaki Sugie
Keyword(s):  
Power Generation ◽  
Fatigue Life ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Power Engineering ◽  
Nuclear Power Generation ◽  
Fatigue Data ◽  
Fatigue Evaluation

Many examinations concerning the fatigue life reduction for structural materials of nuclear power plants in water simulated LWR coolants had been carried out after the first paper had been recognized in Japan [1, 2]. Based on these results, the method to evaluate the fatigue damage for the materials exposed to the LWR coolant had been developed. After 1990s in Japan, the Environmental Fatigue Data Committee (EFD) of the Thermal and Nuclear Power Engineering Society (TENPES), the Project on Environmental Fatigue Testing (EFT) supported by the Japan Power Engineering and Inspection Corporation (JAPEIC) and the Japan Nuclear Energy Safety Organization (JNES) and some utility joint studies have investigated the environmental fatigue. In September 2000, the Nuclear Power Generation Safety Management Division of the Agency for Natural Resources and Energy, Ministry of International Trade and Industry issued “Guidelines for Evaluating Fatigue Initiation Life Reduction in the LWR Environment” (hereafter, called “the MITI Guidelines”) [3]. These guidelines include an equation to evaluate environmental fatigue and require electric utilities to consider the environmental effects in their Plant Life Management (PLM) activities. However, the MITI Guidelines do not provide specific and practical techniques for evaluating environmental fatigue under actual plant conditions. Accordingly, TENPES took on the task to produce one. In 2002 TENPES issued the “Guidelines on Environmental Fatigue Evaluation for LWR Component” [4, 5] (hereafter, called “the TENPES Guidelines”) based on the techniques developed by the EFD Committee. A set of Rules, called the Environmental Fatigue Evaluation Method (EFEM), was established in the Codes for Nuclear Power Generation Facilities - Environmental Fatigue Evaluation Method for Nuclear Power Plants (JSME S NF1-2006, EFEM-2006)[6], which was issued in March 2006 by reviewing the equations for the environmental fatigue life correction factor, Fen, specified in the MITI Guidelines, and the techniques for evaluating environmental fatigue specified in the TENPES Guidelines, and considering the new environmental fatigue data including JNES-SS report (August 2005) [7]. The EFEM revised version has been drafted by incorporating the updated knowledge described in JNES-SS report (April 2007) [8] and is scheduled to be issued by the end of 2009. This paper introduces the revision in it and their technical basis. Additionally, future issues are addressed to be considered in the improvement of the EFEM.

Nontraditional concepts of nuclear power plants with inherent safety (new nuclear technology for the next stage of large-scale production of nuclear power)

Atomic Energy ◽  
1992 ◽  
Vol 72 (4) ◽  
pp. 287-296 ◽  
Author(s):  
V. V. Orlov ◽  
E. N. Avrorin ◽  
E. O. Adamov ◽  
A. P. Vasil'ev ◽  
E. P. Velikhov ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Large Scale ◽  
Nuclear Technology ◽  
Scale Production ◽  
Inherent Safety ◽  
Large Scale Production

scholarly journals Power engineering: Nuclear power plants and renewable energy sources

2017 ◽  
Vol 15 (3) ◽  
pp. 356-366 ◽  
Author(s):  
Alexander Solovyev ◽  
Andrey Pustovgar ◽  
Aleksey Adamtsevich ◽  
Liubov Shilova ◽  
Kirill Degtyarev ◽  
...  
Keyword(s):  
Renewable Energy ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Renewable Energy Sources ◽  
Power Engineering ◽  
Energy Sources

State Oriented Procedure Application in Nuclear Power Plants in China

2010 ◽  
Author(s):  
Qingming Yang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Operating Procedure ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Nuclear Safety ◽  
Nuclear Technology ◽  
Power Plant Operation ◽  
Oriented Approach

With the improvement of nuclear technology and nuclear safety, accidental operating procedure, as an important component of the defence in depth concept for nuclear power plant operation, develops in the way of being more robust and more operator-friendly, especially following the Three Miles Island accident. In China, nuclear power plants try to change from Event Oriented Procedure (EOP) to State Oriented Procedure (SOP) which is a scenario independent approach, developed by French institutes. This paper tries to discuss the principle of the state oriented approach and the composition of SOP. At the same time, comparison between SOP and EOP is made. Having understood the bases of SOP, China Nuclear Power Plants apply it from design to implementation appropriately only.

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