The Experts below are selected from a list of 255 Experts worldwide ranked by ideXlab platform

Joseph I. Braverman - One of the best experts on this subject based on the ideXlab platform.

  • Development of Target Power Spectral Density Functions Compatible With Design Response Spectra
    Volume 8: Seismic Engineering, 2015
    Co-Authors: Jinsuo R. Nie, Joseph I. Braverman
    Abstract:

    For seismic analysis of nuclear structures, synthetic acceleration time histories are often required and are generated to envelop design response spectra following the U.S. Nuclear Regulatory Commission, Standard Review Plan (SRP) Section 3.7.1. It has been recognized that without an additional check of the power spectral density (PSD) functions, spectral matching alone may not ensure that synthetic acceleration time histories have adequate power over the frequency range of interest. The SRP Section 3.7.1 Appendix A provides a target PSD function for the Regulatory Guide 1.60 horizontal spectral shape. For other spectral shapes, additional guidance on developing the target PSD functions compatible with the design spectra is desired. This paper presents a general procedure for the development of target PSD functions for any practical design response spectral shapes, which has been incorporated into the recent SRP 3.7.1, Revision 4.Copyright © 2015 by ASME

  • on the correct application of the 100 40 40 rule for combining responses due to three directions of earthquake loading
    ASME 2010 Pressure Vessels & Piping Conference; Bellevue WA; 20100718 through 20100722, 2010
    Co-Authors: Richard Morante, Manuel J Miranda, Joseph I. Braverman
    Abstract:

    The 100-40-40 rule is often used with the response spectrum analysis method to determine the maximum seismic responses from structural responses resulting from the three spatial earthquake components. This rule has been referenced in several recent Design Certification applications of nuclear power plants, and appears to be gaining in popularity. However, this rule is described differently in ASCE 4-98 and Regulatory Guide 1.92, consequently causing confusion on correct implementation of this rule in practice. The square root of the sum of the squares method is another acceptable spatial combination method and was used to justify the adequacy of the 100-40-40 rule during the development of the Regulatory Guide 1.92. The 100-40-40 rule, when applied correctly, is almost always conservative compared to the SRSS method, and is only slightly unconservative in rare cases. The purpose of this paper is to describe in detail the proper application of the 100-40-40 rule, as prescribed in ASCE 4-98 and in Regulatory Guide 1.92, and to clarify the confusion caused by the two different formats of this rule.

Byung Chul Lee - One of the best experts on this subject based on the ideXlab platform.

  • DEBRIS TRANSPORT ANALYSIS RELATED WITH GSI-191 IN ADVANCED PRESSURIZED WATER REACTOR EQUIPPED WITH INCONTAINMENT REFUELING WATER STORAGE TANK
    2010
    Co-Authors: Jeongik Lee, Soon Joon Hong, Jonguk Kim, Byung Chul Lee
    Abstract:

    A recirculation sump blockage issue is an important and urgent problem to be resolved for ensuring nuclear power plant safety. Through a series of intensive resolution activities, a new Regulatory Guide and an evaluation methodology were proposed. However, these were restricted to a conventional pressurized water reactors (PWRs), and the applicability of these methodologies to a new type or advanced PWR has not been fully addressed. In this paper the applicability of suggested methodologies to a Korean advanced nuclear power plant, which is different from other PWR due to an In-containment Refueling Water Storage Tank (IRWST), is discussed. The scheme for obtaining a solution by using Computational Fluid Dynamic (CFD) is introduced. The CFD was applied to correctly simulate free surface flow. Related mathematical models and numerical analyses are explained in detail. 1

  • debris transport analysis related with gsi 191 in advanced pressurized water reactor equipped with in containment refueling water storage tank
    Experiments and CFD code Applications to Nuclear Reactor Safety, 2008
    Co-Authors: Jeongik Lee, Soon Joon Hong, Jonguk Kim, Byung Chul Lee, Young Seok Bang, Byung Gil Huh
    Abstract:

    A recirculation sump blockage issue is an important and urgent problem to be resolved for ensuring nuclear power plant safety. Through a series of intensive resolution activities, a new Regulatory Guide and an evaluation methodology were proposed. However, these were restricted to a conventional pressurized water reactors (PWRs), and the applicability of these methodologies to a new type or advanced PWR has not been fully addressed. In this paper the applicability of suggested methodologies to a Korean advanced nuclear power plant, which is different from other PWR due to an In-containment Refueling Water Storage Tank (IRWST), is discussed. The scheme for obtaining a solution by using Computational Fluid Dynamic (CFD) is introduced. The CFD was applied to correctly simulate free surface flow. Related mathematical models and numerical analyses are explained in detail.

J V Persio - One of the best experts on this subject based on the ideXlab platform.

  • commercial nuclear reactor loose part monitor setpoints
    Progress in Nuclear Energy, 1999
    Co-Authors: J V Persio
    Abstract:

    Abstract Monitoring and detection of small loose parts within commercial light-water cooled nuclear reactors has been required by regulation in the United States for about 20 years. This monitoring was originally complaint only with Nuclear Regulatory Commission (NRC) Reg Guide 1.133, REV 1, May 1981. The American Society of Mechanical Engineers (ASME) developed an Operations and Maintenance Standard, OM-12, addressing issues which the Regulatory Guide did not address. The Regulatory Guide was prepared prior to significant operating experience which began to unfold during the mid 1980's time frame. This paper reflects upon the history of development for the two standards. Based on available information it concludes that systems meeting the OM-12 requirements are more sensitive to impact-like-events based on a comparison of the detection sensitivities and alert set by each standard. Newer systems meeting OM-12 guidance are not prone to false alarm problems which plagued the first generation systems installed in response to issues discussed in Reg Guide 1.133.

Soon Joon Hong - One of the best experts on this subject based on the ideXlab platform.

  • DEBRIS TRANSPORT ANALYSIS RELATED WITH GSI-191 IN ADVANCED PRESSURIZED WATER REACTOR EQUIPPED WITH INCONTAINMENT REFUELING WATER STORAGE TANK
    2010
    Co-Authors: Jeongik Lee, Soon Joon Hong, Jonguk Kim, Byung Chul Lee
    Abstract:

    A recirculation sump blockage issue is an important and urgent problem to be resolved for ensuring nuclear power plant safety. Through a series of intensive resolution activities, a new Regulatory Guide and an evaluation methodology were proposed. However, these were restricted to a conventional pressurized water reactors (PWRs), and the applicability of these methodologies to a new type or advanced PWR has not been fully addressed. In this paper the applicability of suggested methodologies to a Korean advanced nuclear power plant, which is different from other PWR due to an In-containment Refueling Water Storage Tank (IRWST), is discussed. The scheme for obtaining a solution by using Computational Fluid Dynamic (CFD) is introduced. The CFD was applied to correctly simulate free surface flow. Related mathematical models and numerical analyses are explained in detail. 1

  • a study on improvement of test method of nuclear power plant esf acs by applying Regulatory Guide 1 52 rev 3
    Journal of the Nuclear Fuel Cycle and Waste Technology, 2010
    Co-Authors: Sookkyung Lee, Soon Joon Hong, Kwangsin Kim, Soonhwan Sohn, Kyumin Song, Kaewoo Lee, Jeongseo Park, Byoungho Cho, Byeangjea Yoo, Sunhaeng Kang
    Abstract:

    U. S. NRC Regulation Guide 1.52 regulating ESF ACS in nuclear power plants has been revised to revision 3. To apply reduction of operability test time, allowance of alternative challenge agents for in-place leak test of HEPA filters, and upgrade of Methyl Iodide penetration acceptance criterion in activated carbon performance test suggested in Reg. Guide 1.52(Rev.3) on Yonggwang units 5 and 6 ESF ACSes, technical feasibility study was carried out with on-site experiments as well as experiments with a lab-scale model. It was confirmed that the moisture in the system returned to the level before the test in 1 or 4 days even though the moisture was removed during the operability test lasting more than 10 hours. Therefore, it is appropriate to perform monthly operability test in 15 minutes just long enough to check the operability of equipment. To change challenge material for in-place HEPA filter leak test, size of aerosol, production rate, and leak detection capability were compared for DOP and PAO. It was concluded that PAO can be substituted for DOP in nuclear power plants. The upgrade of Methyl Iodide penetration acceptance criterion from 0.175 % to 0.5 % in active carbon filter bed deeper than 4 inches was to conform to the change of activated carbon performance test method to ASTM D3803(1989). It was confirmed that Methyl Iodide penetration acceptance criterion of 0.5 % under , relative humidity 95 % condition was conservatively good enough for testing performance of active carbon insitu. The licence change of Yonggwang units 5 and 6 has been completed based on this study.

  • debris transport analysis related with gsi 191 in advanced pressurized water reactor equipped with in containment refueling water storage tank
    Experiments and CFD code Applications to Nuclear Reactor Safety, 2008
    Co-Authors: Jeongik Lee, Soon Joon Hong, Jonguk Kim, Byung Chul Lee, Young Seok Bang, Byung Gil Huh
    Abstract:

    A recirculation sump blockage issue is an important and urgent problem to be resolved for ensuring nuclear power plant safety. Through a series of intensive resolution activities, a new Regulatory Guide and an evaluation methodology were proposed. However, these were restricted to a conventional pressurized water reactors (PWRs), and the applicability of these methodologies to a new type or advanced PWR has not been fully addressed. In this paper the applicability of suggested methodologies to a Korean advanced nuclear power plant, which is different from other PWR due to an In-containment Refueling Water Storage Tank (IRWST), is discussed. The scheme for obtaining a solution by using Computational Fluid Dynamic (CFD) is introduced. The CFD was applied to correctly simulate free surface flow. Related mathematical models and numerical analyses are explained in detail.

Jeongik Lee - One of the best experts on this subject based on the ideXlab platform.

  • DEBRIS TRANSPORT ANALYSIS RELATED WITH GSI-191 IN ADVANCED PRESSURIZED WATER REACTOR EQUIPPED WITH INCONTAINMENT REFUELING WATER STORAGE TANK
    2010
    Co-Authors: Jeongik Lee, Soon Joon Hong, Jonguk Kim, Byung Chul Lee
    Abstract:

    A recirculation sump blockage issue is an important and urgent problem to be resolved for ensuring nuclear power plant safety. Through a series of intensive resolution activities, a new Regulatory Guide and an evaluation methodology were proposed. However, these were restricted to a conventional pressurized water reactors (PWRs), and the applicability of these methodologies to a new type or advanced PWR has not been fully addressed. In this paper the applicability of suggested methodologies to a Korean advanced nuclear power plant, which is different from other PWR due to an In-containment Refueling Water Storage Tank (IRWST), is discussed. The scheme for obtaining a solution by using Computational Fluid Dynamic (CFD) is introduced. The CFD was applied to correctly simulate free surface flow. Related mathematical models and numerical analyses are explained in detail. 1

  • debris transport analysis related with gsi 191 in advanced pressurized water reactor equipped with in containment refueling water storage tank
    Experiments and CFD code Applications to Nuclear Reactor Safety, 2008
    Co-Authors: Jeongik Lee, Soon Joon Hong, Jonguk Kim, Byung Chul Lee, Young Seok Bang, Byung Gil Huh
    Abstract:

    A recirculation sump blockage issue is an important and urgent problem to be resolved for ensuring nuclear power plant safety. Through a series of intensive resolution activities, a new Regulatory Guide and an evaluation methodology were proposed. However, these were restricted to a conventional pressurized water reactors (PWRs), and the applicability of these methodologies to a new type or advanced PWR has not been fully addressed. In this paper the applicability of suggested methodologies to a Korean advanced nuclear power plant, which is different from other PWR due to an In-containment Refueling Water Storage Tank (IRWST), is discussed. The scheme for obtaining a solution by using Computational Fluid Dynamic (CFD) is introduced. The CFD was applied to correctly simulate free surface flow. Related mathematical models and numerical analyses are explained in detail.