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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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 RPD
Wednesday, June 16, 2021|2:15–4:00PM EDT
Session Chair:
Kristin Stolte (TAMU)
Session Organizer:
Pavel V. Tsvetkov (TAMU)
Staff Producer:
Julie Bry (ANS)
This is a standing RPD session with papers on all general reactor physics topics of contemporary interest.
To access the session recording, you must be logged in and registered for the meeting.
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To access paper attachments, you must be logged in and registered for the meeting.
Multi-Physics Sensitivity Analysis of BEAVRS 1st Cycle using MPCORE
Alexey Cherezov (Ulsan Nat'l Institute of Science and Technology), Awais Zahur (Ulsan Nat'l Institute of Science and Technology), Chidong Kong (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)
Summary
Reactivity Underestimation of ENDF/B-VIII.0 Compared with ENDF/B-VII.1 for the Pressurized Water Reactor Depletion Analysis
Kang-Seog Kim (ORNL), William A. Wieselquist (ORNL)
Using MCNP and NJOY to Verify Charged Particle Data in CP2020
D. Kent Parsons (LANL), Cecile Toccoli (LANL)
Pre-Conceptual Design of a Gas-Cooled Microreactor with Two-Phase Composite Moderators
Edward M. Duchnowski (Univ. of Tennessee Knoxville), Robert F. Kile (Univ. of Tennessee Knoxville), Jacob P. Gorton (Univ. of Tennessee Knoxville), Nicholas R. Brown (Univ. of Tennessee Knoxville)
A Benchmark Model for Kairos Power's Pebble-Bed Fluoride-Salt-Cooled High Temperature Reactor
Nader Satvat (Kairos Power), Fatih Sarikurt (Kairos Power), Kevin Johnson (Kairos Power), Ian Kolaja (Kairos Power), Massimiliano Fratoni (Univ. of California Berkeley)
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