Energy in the 1980s - Operational experience in nuclear power stations

1974 ◽  
Vol 276 (1261) ◽  
pp. 571-586
Keyword(s):  
Nuclear Power ◽  
Nuclear Energy ◽  
Large Scale ◽  
Electrical Power ◽  
Operating Experience ◽  
Operational Experience ◽  
Original Design ◽  
Safety Requirements ◽  
Design Concepts ◽  
Power Stations

From the first self-sustaining nuclear reaction to the present day represents a span of three decades: within that time large-scale generation of electrical power from nuclear energy has become acknowledged as economic, safe and environmentally acceptable. Within the U .K . 10% of electricity consumed is of nuclear origin. Some of the C.E.G.B. reactors have been in service for over 10 years. The operating experience that has been gained shows how the original design concepts have been ultimately developed. Some of the difficulties encountered and the engineering solutions are presented. Operating experience feeds back to the design philosophy and safety requirements for future nuclear plant. In this way a foundation is provided for the further exploitation of what must become a major source of energy in the next decade.

Nuclear fission

2007 ◽  
Author(s):  
Sue Ion
Keyword(s):  
Energy Supply ◽  
Nuclear Power ◽  
Large Scale ◽  
Nuclear Reactor ◽  
Nuclear Fission ◽  
Fuel Rods ◽  
Power Stations ◽  
Key Issues ◽  
Burning Coal ◽  
Hollow Metal

This chapter will cover the nuclear fission option as a future energy supply, and will essentially address the question: can nuclear fission plug the gap until the potential of nuclear fusion is actually realized? (The potential for fusion is considered in detail chapter 7.) To put this question into context, let us first look at some of the key issues associated with nuclear fission, which currently supplies around one fifth of the UK’s electricity. Most large scale power stations produce electricity by generating steam, which is used to power a turbine. In a nuclear power station, the principle is the same, but instead of burning coal, oil, or gas to turn water into steam, the heat energy comes from a nuclear reactor. A reactor contains nuclear fuel, which remains in place for several months at a time, but over that time it generates a huge amount of energy. The fuel is usually made of uranium, often in the form of small pellets of uranium dioxide, a ceramic, stacked inside hollow metal tubes or fuel rods, which can be anything from a metre to four metres in length, depending on the reactor design. Each rod is about the diameter of a pencil, and the rods are assembled into carefully designed bundles, which in turn are fixed in place securely within the reactor. There are two isotopes (or different types) of uranium, and only one of these is a material which is ‘fissionable’—that is to say, if an atom of this uranium isotope is hit by a neutron, then it can split into two smaller atoms, giving off energy in the process and also emitting more neutrons. This, and other pathways, are illustrated in Fig. 6.1 (Source: CEA). Controlling the reaction, so that the energy from the fission of uranium atoms is given out slowly over a period of years, requires two aspects of the process to be carefully balanced. 1. First, there must be enough fissile atoms in the fuel so that—on average— each fission leads to exactly one other. Any fewer, and the reaction will die away.

Circulator Design/Technology Evolution for Gas-Cooled Nuclear Reactors

1992 ◽  
Author(s):  
Colin F. McDonald ◽  
Ian R. Marshall ◽  
John Donaldson ◽  
Davdrin D. Kapich
Keyword(s):  
Nuclear Power ◽  
State Of The Art ◽  
Nuclear Reactors ◽  
Power Conversion ◽  
Electrical Power ◽  
Operating Experience ◽  
Lessons Learned ◽  
Future Trends ◽  
Design Technology ◽  
Conversion System

The circulator is a key component in a gas-cooled nuclear power plant since it facilitates transfer of the reactor thermal energy (via the steam generator) to the electrical power conversion system. Circulator technology is well established and about 200 machines, which, in their simplest form, consist of an electrical motor driven compressor, have operated for many millions of hours worldwide in gas-cooled reactors. This paper covers the evolution of circulator design, technology and operating experience, with particular emphasis on how lessons learned over the last four decades (dominantly from the carbon dioxide cooled plants in the U.K.) are applicable to the helium cooled Modular High Temperature Gas-Cooled Reactor (MHTCR) which should see service in the U.S. at the turn of the next century. State-of-the-art technologies are covered in the areas of impeller selection, bearings, drive system, machine operation, and future trends are Identified.

scholarly journals International cooperation in the sphere of peaceful uses of nuclear energy as a resolution of energy supply and nuclear proliferation problems

2009 ◽  
pp. 163-174
Author(s):  
M. V. Zharkih
Keyword(s):  
Comparative Analysis ◽  
International Cooperation ◽  
Nuclear Power ◽  
Nuclear Energy ◽  
Large Scale ◽  
Fuel Cycle ◽  
Nuclear Proliferation ◽  
Advantages And Disadvantages ◽  
The Us ◽  
Made In

Comparative analysis of the Russian and the US initiatives. The article gives an outline of such a promising branch of international cooperation as cooperation in the sphere of peaceful uses of nuclear energy, in particularly its multilateral aspects – initiatives of States based on the multilateral principle of uses of nuclear power. The comparative analysis of the two large-scale initiatives in the field ofmultilateral approaches to the nuclear fuel cycle – these are the Russian initiative on the development of the Global infrastructure of nuclear energy and the American Global nuclear energy partnership –made in the article discloses the main principles of work of the abovementioned mechanisms of interaction as well as their advantages and disadvantages. The goal of such an analysis is to figure out which one has a greater potential for international security and future development of the nuclear energy sector.

Efficient Power Generation From Large 750°C Heat Sources: Application to Coal-Fired and Nuclear Power Stations

1980 ◽  
Author(s):  
Z. P. Tilliette ◽  
B. Pierre
Keyword(s):  
Power Generation ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Energy ◽  
Inlet Temperature ◽  
Heat Sources ◽  
Turbine Inlet Temperature ◽  
Power Stations ◽  
Efficient Power ◽  
Steam Cycle

Considering the concern about a more efficient, rational use of heat sources, and a greater location flexibility of power plants owing to cooling capability, closed gas cycles can offer new solutions for fossil or nuclear energy. An efficient heat conversion into power is obtained by the combination of a main non-intercooled helium cycle with a flexible, superheated, low-pressure bottoming steam cycle. Emphasis is placed on the matching of the two cycles and, for that, a recuperator bypass arrangement is used. The operation of the main gas turbocompressor does not depend upon the operation of the small steam cycle. Results are presented for a conservative turbine inlet temperature of 750 C. Applications are made for a coal-fired power plant and for a nuclear GT-HTGR. Overall net plant efficiencies of 39 and 46 percent, respectively, are projected.

Operational Impacts and Consequences of Piping Component Failure: A Review of Operating Experience Data As Recorded in CODAP

2018 ◽  
Author(s):  
Braedon Carr ◽  
Bengt Lydell ◽  
Jovica R. Riznic
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Cooling Water ◽  
Operating Experience ◽  
Transport Systems ◽  
Volume Control ◽  
Operational Experience ◽  
Component Failure ◽  
Plant Safety ◽  
Operational Impacts

Water chemistry plays an important part in maintaining corrosion resistance in water transport systems throughout nuclear power plants (NPP’s). Small changes in liquid chemistry such as pH, borate concentration, or build-up of crud in reactor cooling water can result in rapid degradation or damage to components and lead to unexpected failures. The Chemical and Volume Control System (CVCS) and Reactor Water Cleanup System (RWCU) are responsible for maintaining these parameters at appropriate levels, and so failure of either of these systems can result in unnecessary stresses on many other reactor systems due to resulting transients. While the major components of these systems all have sufficient redundancy to prevent major accidents, failure of components in these systems can result in failure of other redundant components and affect plant safety [1]. The CVCS and RWCU systems have experienced aging related degradations and failures in the past, and although they have not affected the system’s emergency functions, they have resulted in unnecessary actuation of related systems, and reactor shutdowns [1]. Reactor shutdowns can result in large changes in reactor coolant chemistry such as oxygen and borate concentration transients, and the build-up of corrosion products which can’t be as easily removed during periods of reactor shutdown [2]. In the following analysis of Component Operational Experience Degradation and Ageing Program (CODAP) experience data; causes, impacts, and preventative actions as recorded in CODAP are examined for degradation events which took place in the CVCS and RWCU, of PWRs and BWRs, respectively. The analysis will demonstrate the usefulness of CODAP in examining reactor component failure trends, as well as discuss insights on improvement for the program.

Life Prediction and Monitoring of Nuclear Power Plant Components for Service-Related Degradation

2000 ◽  
Vol 123 (1) ◽  
pp. 58-64 ◽  
Author(s):  
Fredric A. Simonen ◽  
Stephen R. Gosselin
Keyword(s):  
Life Prediction ◽  
Nuclear Power ◽  
Fatigue Crack Initiation ◽  
Operating Experience ◽  
Degradation Mechanisms ◽  
Original Design ◽  
Structural Degradation ◽  
Plant Safety ◽  
Degradation Data ◽  
Design Life

This paper describes industry programs to manage structural degradation and to justify continued operation of nuclear components when unexpected degradation has been encountered due to design materials and/or operational problems. Other issues have been related to operation of components beyond their original design life in cases where there is no evidence of fatigue crack initiation or other forms of structural degradation. Data from plant operating experience have been applied in combination with inservice inspections and degradation management programs to ensure that the degradation mechanisms do not adversely impact plant safety. Probabilistic fracture mechanics calculations are presented to demonstrate how component failure probabilities can be managed through augmented inservice inspection programs.

scholarly journals Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea

2013 ◽  
Vol 2013 ◽  
pp. 1-18 ◽  
Author(s):  
Yeong-il Kim ◽  
Yong Bum Lee ◽  
Chan Bock Lee ◽  
Jinwook Chang ◽  
Chiwoong Choi
Keyword(s):  
Fast Reactor ◽  
Electricity Generation ◽  
Nuclear Power ◽  
Large Scale ◽  
Development Program ◽  
Energy Resources ◽  
Test Facility ◽  
Current Status ◽  
Hydraulic Test ◽  
Design Concepts

Korea imports about 97% of its energy resources due to a lack of available energy resources. In this status, the role of nuclear power in electricity generation is expected to become more important in future years. In particular, a fast reactor system is one of the most promising reactor types for electricity generation, because it can utilize efficiently uranium resources and reduce radioactive waste. Acknowledging the importance of a fast reactor in a future energy policy, the long-term advanced SFR development plan was authorized by KAEC in 2008 and updated in 2011 which will be carried out toward the construction of an advanced SFR prototype plant by 2028. Based upon the experiences gained during the development of the conceptual designs for KALIMER, KAERI recently developed advanced sodium-cooled fast reactor (SFR) design concepts of TRU burner that can better meet the generation IV technology goals. The current status of nuclear power and SFR design technology development program in Korea will be discussed. The developments of design concepts including core, fuel, fluid system, mechanical structure, and safety evaluation have been performed. In addition, the advanced SFR technologies necessary for its commercialization and the basic key technologies have been developed including a large-scale sodium thermal-hydraulic test facility, super-critical Brayton cycle system, under-sodium viewing techniques, metal fuel development, and developments of codes, and validations are described as R&D activities.

Space solar power may solve key renewables challenge

2021 ◽  
Keyword(s):  
Renewable Energy ◽  
Nuclear Power ◽  
Large Scale ◽  
Solar Power ◽  
Energy System ◽  
Content Type ◽  
Design Concepts ◽  
Space Solar Power ◽  
Launch Systems ◽  
National Infrastructure

Significance Using satellites to collect solar power in space and transmit it to earth to generate electricity overcomes a serious limitation of terrestrial renewable energy: its intermittency. As such, it could enable transition to a wholly renewable energy system. Impacts Design concepts vary, but generally envisage each satellite generating an amount of electricity on a par with a nuclear power plant. Placing critical national infrastructure in space would both hasten the militarisation of space and add urgency to arms control initiatives. Large-scale funding for SBSP would spur development of supporting technologies and spin-offs, including robotics and launch systems.

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