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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
2022 ANS Annual Meeting
June 12–16, 2022
Anaheim, CA|Anaheim Hilton
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Science and Engineering
Fusion Science and Technology
Cost drivers of nuclear steam cycle construction
Interest in reducing carbon emissions around the world continues to climb. As a complement to the increasing deployment of variably generating renewables, advanced nuclear is commonly shown in net-zero grid modeling for 2050 because it represents firm electricity production that can flex in output with load demands.1 However, these projections are challenged by the high levelized cost of electricity associated with legacy nuclear construction, which is often more than double that of modern combined-cycle gas turbine (CCGT) plants.
12th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2021)
Thursday, June 17, 2021|9:00–10:45AM (10:00–11:45AM EDT)
Markus Porthin (Paul Scherrer Institut)
Sung-Min Shin (KAERI)
Pat Schroeder (ANS)
This session will also include a panel discussion on the research and development needs concerning reliability modeling of digital I&C.
Hongbin Zhang (INL)
Sung-Min Shin (KAERI)
Hyun Gook Kang (Rensselaer Polytechnic Institute)
Paolo Picca (Office For Nuclear Regulation)
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Integrated Risk Assessment of Digital I&C Safety Systems for Nuclear Power Plants
Hongbin Zhang (INL), Han Bao (INL), Tate Shorthill (Univ. of Pittsburgh), Edward Quinn (Technology Resources)
WGRISK DIGMAP: Comparison of PSA Modeling Approaches for Digital I&C
Markus Porthin (Paul Scherrer Institut), Sung-Min Shin (KAERI), Milan Jaros (ÚJV Řež), Jiri Sedlak (ÚJV Řež), Paolo Picca (Office for Nuclear Regulation), Richard Quatrain (EDF), Jeanne Demgné (EDF), Hans Brinkman (NRG), Venkat Natarajan (NRG), Tero Tyrväinen (VTT Technical Research Centre of Finland), Christian Müller (Gesellschaft fuer Anlagen- und Reaktorsicherheit), Ewgenij Piljugin (Gesellschaft fuer Anlagen- und Reaktorsicherheit)
Risk Comparison Among Design Options of RPS with Diverse PLC and FPGA Systems
Hyun Gook Kang (Rensselaer Polytechnic Institute), Kwang-Seop Son (KAERI), Seung Hwan Seong (KAERI)
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