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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
Standards Program
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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Nov 2022
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Nuclear Science and Engineering
November 2022
Nuclear Technology
December 2022
Fusion Science and Technology
Latest News
Route readiness elements in a large-scale spent nuclear fuel transportation system
The scale and duration of a national campaign to transport spent nuclear fuel (SNF) from commercial nuclear power plants around the United States would be unprecedented. A meticulous level of planning that considers many elements is needed to inspire public confidence and support.
Technical Session|Sponsored by THD
Wednesday, June 16, 2021|12:00–1:45PM EDT
Session Chair:
Robert P. Martin
Alternate Chair:
Dillon R. Shaver
Session Organizer:
Matthew D. Zimmer
Staff Producer:
Jessie Vazquez (ANS)
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Thermal Decomposition of Carbonates as a Passive Cooling Mechanism for Molten Salt Reactors
Christopher Forsyth (Univ. of California, Berkeley)
Summary
Study of Sodium Pool Fire Model Improvement in MELCOR for SFR
David L.Y. Louie (Sandia National Laboratories), Mitsuhiro Aoyagi (Japan Atomic Energy Agency)
Thermal Hydraulic Modeling of the Kairos Power Generic Fluoride High Temperature Reactor in MELCOR
Robert F. Kile (Univ. of Tennessee Knoxville), Friederike Bostelmann (ORNL), Steve E. Skutnik (ORNL), William A. Wieselquist (ORNL), Nicholas R. Brown (Univ. of Tennessee Knoxville)
Modeling of HTTF test PG-26 using RELAP5-3D and SAM
Aaron Epiney (INL), Thanh Hua (ANL), James Wolf (INL), Ling Zou (ANL), Gerhard Strydom (INL), Rui Hu (ANL)
Safety Assessment of Composite Alternative Moderators for Modular High Temperature Gas-Cooled Reactors
Veronica Karriem (Univ. of Tennessee Knoxville), Edward M. Duchnowski (Univ. of Tennessee Knoxville), Nicholas R. Brown (Univ. of Tennessee Knoxville)
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