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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.
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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
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 FCWMD
Wednesday, June 16, 2021|4:30–6:15PM EDT
Christina Leggett (Booz Allen Hamilton)
Benjamin B. Cipiti (Sandia National Laboratories)
Mich Leana (ANS)
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Elastic Waveform Tomography of Spent Nuclear Fuel Casks
Othman Oudghiri-Idrissi (Univ. of Minnesota), Mohammad HanifehZadeh (Univ. of Southern California), Bora E. Gencturk (Univ. of Southern California), Roger G. Ghanem (Univ. of Southern California), Bojan B. Guzina (Univ. of Minnesota)
Oxalic Acid Dissolution System for Mercury Recovery Process Optimization
Michael Smith (Univ. of North Carolina at Charlotte), Sven Bader (Orano Federal Services), Thomas Koch (Univ. of North Carolina at Charlotte), Arthur Niemoller (Orano Federal Services), Andrew Straight (Univ. of North Carolina at Charlotte)
SMR Gadolinia Burnable Absorber Loading Design in a No-Onsite Refueling Core Neutronics Performance Assessment
Gray Chang (JFoster and Associates), Julie Foster (JFoster and Associates), Jim Harrell (Zachry Nuclear), Mie Hiruta (JFoster & Assoc.)
Comparison of Desiccation Cracks between Bentonite and Inorganic Microfiber Reinforced Bentonite for Engineered Barrier System
Yuan Feng (Univ. of Nebraska-Lincoln), Jongwan Eun (Univ. of Nebraska-Lincoln), Seunghee Kim (Univ. of Nebraska-Lincoln), Yong-Rak Kim (Texas A&M Univ.)
Development of a Heat Signature Computational Simulation for Safeguarded Spent Nuclear Fuel
Alvaro Pizarro-Vallejos (Univ. of Illinois Urbana Champaign), Michael D. Kaminski (ANL), Jeffrey Fortner (ANL)
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