Strategies for Improved Nuclear Plant Reliability

1983 ◽  
Vol 105 (2) ◽  
pp. 171-177
Author(s):  
J. M. Thomas ◽  
P. R. Bosinoff

This paper presents a methodology for identifying cost-effective failure prevention strategies for components or systems in nuclear power plants. Two strategies identified are the improvement of component reliability and the addition of redundant components. These two strategies are evaluated within the context of both repairable and nonrepairable systems. Capacity/demand and continuous time models are used to analyze the two strategies and systems. An example problem is developed for a continuous time, repairable system. It is clearly shown that large expenditures are justified to improve the reliability of some major systems in nuclear power plants and that these expenditures, exceeding the original capital cost of the system, could save tens of millions of dollars.

Author(s):  
E. J. Butcher ◽  
J. W. Roe

The September 11, 2001 terrorist attack on the World Trade Center and subsequent events has effected perceptions of the terrorist threat to the U.S. in general, and nuclear power plants in particular. These concerns have given rise to calls by government and private orga nizations for reevaluations of both the nature of the threat and protection against it. This paper suggests a general framework for a balanced approach to these reevaluations and highlights some practical and cost effective approaches for improving nuclear power plant safeguards protection.


Author(s):  
Sung Goo Chi ◽  
Seok Jeong Park ◽  
Chul Jin Choi ◽  
S. E. Ritterbusch ◽  
M. C. Jacob

Westinghouse Electric Company (WEC) has been working with Korea Power Engineering Company (KOPEC) on a US Department of Energy (DOE) sponsored Nuclear Energy Research Initiative (NERI) project through a collaborative agreement established for the domestic NERI program. The project deals with Risk-Informed Assessment (RIA) of regulatory and design requirements of future nuclear power plants. An objective of the RIA project is to develop a risk-informed design process, which focuses on identifying and incorporating advanced features into future nuclear power plants (NPPs) that would meet risk goals in a cost-effective manner. The RIA design methodology is proposed to accomplish this objective. This paper discusses the development of this methodology and demonstrates its application in the design of plant systems for future NPPs. Advanced conceptual plant systems consisting of an advanced Emergency Core Cooling System (ECCS) and Emergency Feedwater System (EFWS) for a NPP were developed and the risk-informed design process was exercised to demonstrate the viability and feasibility of the RIA design methodology. Best estimate Loss-of-Coolant Accident (LOCA) analyses were performed to validate the PSA success criteria for the NPP. The results of the analyses show that the PSA success criteria can be met using the advanced conceptual systems and that the RIA design methodology is a viable and appropriate means of designing key features of risk-significant NPP systems.


Author(s):  
Marcel Tortolano ◽  
Jacques Guillet

EDF is the French national power generating utility. It has built and operates 58 pressurized water reactor (PWR) nuclear power plants on 19 sites. Of these, thirty-four are 900 megawatt units (the first of which, the Fessenheim NPP, came on line in 1977), twenty are 1300 MW units, and four are 1450 MW units, the latest of which, at the Civaux plant, came on line in 1998. The average age of these nuclear power plants is thus 20 years. They produce close to 85% of the power EDF generates in France. Renewal of the nuclear plants is under study, as are other means of power generation. For the moment, EDF is requesting approval to run its nuclear plants for up to 40 years. Moreover, it has started a major project on the lifetime of PWR reactors, the main objective of which is to extend the authorized lifetime to 60 years. Major requirements for maintaining the current performance of the French nuclear generating facility and reducing the cost per kWh generated include optimization of expenses and reduction of fuel costs. These factors enabled the cost per kWh to be reduced by 13% in 2001. One way to reduce costs involves optimization of maintenance programs and methods. However, increasing the operating lifetime of plants, and the concomitant ageing of equipment and materials, is likely to result in increasing maintenance requirements. For this reason it is important to establish new, more cost-effective maintenance methods in order to keep costs down. Some of these methods make use of robotics. They make it possible for work to be carried out from the inside of circuits, for inspections and even for repair if defects are detected. The results presented here are those of work carried out by the EDF R&D division on behalf of the Nuclear Power Plant Operations (NPPO) division.


Author(s):  
Marjorie B. Bauman ◽  
Richard F. Pain ◽  
Harold P. Van Cott ◽  
Margery K. Davidson

2010 ◽  
pp. 50-56 ◽  
Author(s):  
Pablo T. León ◽  
Loreto Cuesta ◽  
Eduardo Serra ◽  
Luis Yagüe

Author(s):  
R. Z. Aminov ◽  
A. N. Bayramov ◽  
M. V. Garievskii

The paper gives the analysis of the problem of the primary current frequency regulation in the power system, as well as the basic requirements for NPP power units under the conditions of involvement in the primary regulation. According to these requirements, the operation of NPPs is associated with unloading and a corresponding decrease in efficiency. In this regard, the combination of nuclear power plants with a hydrogen complex is shown to eliminate the inefficient discharge mode which allows the steam turbine equipment and equipment of the reactor facility to operate in the basic mode at the nominal power level. In addition, conditions are created for the generation and accumulation of hydrogen and oxygen during the day, as well as additionally during the nighttime failure of the electrical load which allows them to be used to generate peak power.  The purpose of the article is to assess the systemic economic effect as a result of the participation of nuclear power plants in combination with the hydrogen complex in the primary control of the current frequency in the power sys-tem, taking into account the resource costs of the main equipment. In this regard, the paper gives the justification of cyclic loading of the main equipment of the hydrogen complex: metal storage tanks of hydrogen and oxygen, compressor units, hydrogen-oxygen combustion chamber of vapor-hydrogen overheating of the working fluid in the steam turbine cycle of a nuclear power plant. The methodological foundations for evaluating the working life of equipment under cyclic loading with the participation in the primary frequency control by the criterion of the growth rate of a fatigue crack are described. For the equipment of the hydrogen complex, the highest intensity of loading is shown to occur in the hydrogen-oxygen combustion chamber due to high thermal stresses.  The system economic effect is estimated and the effect of wear of the main equipment under cyclic loading is shown. Under the conditions of combining NPP power units with a hydrogen complex, the efficiency of primary reg-ulation is shown to depend significantly on: the cost of equipment subjected to cyclic loading; frequency and intensity of cyclic loading; the ratio of the tariff for peak electricity, and the cost of electricity of nuclear power plants.  Based on the developed methodology for assessing the effectiveness of the participation of nuclear power plants with a hydrogen complex in the primary frequency control, taking into account the damage to the equipment, the use of the hydrogen complex is shown to provide a tangible economic effect compared with the option of unloading nuclear power plants with direct participation in frequency control.


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