scholarly journals Study on initial crack assumed in the flaw tolerance approach applied to piping of nuclear power plants

2019 ◽  
Vol 85 (874) ◽  
pp. 18-00422-18-00422
Author(s):  
Shuhei TAKEDA ◽  
Seiji ASADA
Author(s):  
C. K. Ng ◽  
S. F. Hankinson ◽  
M. Salac ◽  
S. A. Swamy

Evaluation of metal fatigue is one of the identified Time Limited Aging Analyses (TLAA) described in the License Renewal Applications for nuclear power plants. A related area is the evaluation of Environmentally Assisted Fatigue (EAF) as required by the Nuclear Regulatory Commission (NRC) in the United States. The focus is on fatigue sensitive components in power plants selected based on anticipated loading conditions and service experience. The pressurizer surge line was identified as a representative component for the evaluation of EAF for nuclear power plants of both older and newer vintage. A particular location of interest on the surge line is the surge line hot leg nozzle to pipe weld. Typical resolution of EAF concerns in a License Renewal Application requires the incorporation of large Environmental Fatigue Multipliers (Fen) in determining the cumulative usage factors for austenitic stainless steel components. Consequently, the 60-year projected cumulative usage factor at this weld location of interest has the potential to exceed the ASME Section III Code allowable limit of 1.0. For components that fail to demonstrate that the predicted cumulative usage factor is less than 1.0, ASME Section XI Non-Mandatory Appendix L provides guidance for evaluating the component’s fitness for service. The approach is based on a fatigue flaw tolerance evaluation and the implementation of an inspection strategy to demonstrate that growth of a postulated flaw would remain below the allowable flaw size for the component of interest. NUREG/CR-6934 establishes a technical basis for improvements to the initially published version of Appendix L requirements. These improvements have been incorporated in the 2008 Addenda to ASME Section XI Code. One of the improvements is the use of Equivalent Single Crack (ESC) aspect ratio to account for the effects of multiple fatigue crack initiations and the linking of these cracks as they grow to form a single long crack with large aspect ratio. Since the NRC in the United States has not yet endorsed the use of 2008 Addenda to the ASME Section XI Code which contains the latest version of Appendix L, fatigue flaw tolerance analysis is performed in accordance with the requirements in NUREG/CR-6934 for the current license renewal applications. This paper demonstrates the use of the fatigue flaw tolerance approach in accordance with the requirements in NUREG/CR-6934. Typical thermal stratification loading and thermal transients including the use of ESC aspect ratios are considered in the fatigue flaw tolerance evaluation. The results are used to demonstrate fitness for service for a typical 14-inch Schedule 160 pressurizer surge line when the predicted cumulative usage factor exceeds 1.0 for 60 years of plant operation.


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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