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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)
Tuesday, June 15, 2021|11:00AM–12:45PM (12:00–1:45PM EDT)
Josh Daw (INL)
Fan Zhang (University of Tennessee-Knoxville)
Jamie B. Coble (University of Tennessee-Knoxville)
Janet Davis (ANS)
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Dynamic Response Characterization of Temperature Sensors for Small Modular Reactors
A. H. Hashemian (Analysis and Measurement Services Corp.), E. T. Riggsbee (Analysis and Measurement Services Corp.), S. N. Tyler (Analysis and Measurement Services Corp.), B. Arnholt (NuScale Power), N. Cetiner (ORNL)
Development and Testing of High Temperature Fiber Optic Sensors for Measurement of Heat Pipe Temperature in the eVinci™ Micro Reactor
Thomas Tweedle (Westinghouse Electric Co.), Yuqi Li (Univ. of Pittsburgh), Kevin Chen (Univ. of Pittsburgh)
Microwave Resonant Cavity-Based Flow Sensor for Advanced Reactor High Temperature Fluids
Alexander Heifetz (ANL), Victoria Ankel (ANL), Dmitry Shribak (ANL), Sasan Bakhtiari (ANL), Anthonie Cilliers (Kairos Power)
Design, Fabrication, Installation and Operation of the In-Core Instrumentation for EPR Reactors
Patrick Weidenauer (Framatome), Heiko Jasper (Framatome)
The Transient Thermal Response of a Pressure-Driven Fabry-Pérot Cavity
Daniel C. Sweeney (ORNL), Adrian M. Schrell (ORNL), Christian M. Petrie (ORNL)
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