Zobrazeno 1 - 10
of 21
pro vyhledávání: '"Charles H. Hofmayer"'
Autor:
Young-Sun Choun, Min-Kyu Kim, Jinsuo Nie, Joseph I. Braverman, In-Kil Choi, Charles H. Hofmayer
Publikováno v:
Nuclear Engineering and Technology. 44:297-310
Aging-related degradation of nuclear power plant components is an important aspect to consider in securing the long term safety of the plant, especially the seismic safety, since the degradation of the components affects not only their seismic capaci
Autor:
D.J. Naus, Joseph I. Braverman, Charles H. Hofmayer, C.A. Miller, T. Y. Chang, Bruce R. Ellingwood
Publikováno v:
Nuclear Engineering and Design. 228:283-304
This paper describes a multi-year research program to assess age-related degradation of structures and passive components important to the safe operation of nuclear power plants (NPPs). The purpose of the research effort is to develop the technical b
Autor:
Charles H. Hofmayer, Young-Sun Choun, Min-Kyu Kim, Joseph I. Braverman, In-Kil Choi, Jinsuo R. Nie
Publikováno v:
Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles.
The Korea Atomic Energy Research Institute (KAERI) and Brookhaven National Laboratory (BNL) are continuing a collaborative effort to achieve a better understanding of the effects of aging on the performance of structures and passive components (SPCs)
Autor:
Charles H. Hofmayer, Syed A. Ali, Frederick W. Brust, Do-Jun Shim, Jinsuo Nie, Tao Zhang, Gery Wilkowski
Publikováno v:
Journal of Pressure Vessel Technology. 134
Nuclear power plant safety under seismic conditions is an important consideration. The piping systems may have some defects caused by fatigue, stress corrosion cracking, etc., in aged plants. These cracks may not only affect the seismic response but
Publikováno v:
Volume 8: Seismic Engineering.
The licensing framework established by the U.S. Nuclear Regulatory Commission under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” provides requirements for standa
Publikováno v:
ASME 2010 Pressure Vessels and Piping Conference: Volume 8.
Demonstrating the structural integrity of U.S. nuclear power plant (NPP) containment structures, for beyond design-basis internal pressure loadings, is necessary to satisfy Nuclear Regulatory Commission (NRC) requirements and performance goals. This
Autor:
Tao Zhang, Charles H. Hofmayer, Frederic W. Brust, Syed A. Ali, Jinsuo Nie, Gery Wilkowski, Do-Jun Shim
Publikováno v:
ASME 2010 Pressure Vessels and Piping Conference: Volume 8.
Nuclear power plant safety under seismic conditions is an important consideration. The piping systems may have some defects caused by fatigue, stress corrosion cracking, etc., in aged plants. These cracks may not only affect the seismic response, but
Publikováno v:
ASME 2010 Pressure Vessels and Piping Conference: Volume 8.
The specification of damping for nuclear piping systems subject to seismic-induced motions has been the subject of many studies and much controversy. Damping estimation based on test data can be influenced by numerous factors, consequently leading to
Autor:
Charles H. Hofmayer, K. Bandyopadhyay
Publikováno v:
Nuclear Engineering and Design. 134:311-317
An evaluation of the existing relay test data base at Brookhaven National Laboratory (BNL) has indicated that the seismic capacity of a relay may depend on various parameters related to the design or the input motion. In order to investigate the effe