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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2022 ANS Annual Meeting
June 12–16, 2022
Anaheim, CA|Anaheim Hilton
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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June 2022
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Latest News
Deadline extended to apply for ANS's 2023 ANS Congressional Fellowship
The deadline for applications to the ANS's Glenn T. Seaborg Congressional Science and Engineering Fellowship has been extended. All ANS members are invited to apply to help the Society fulfill its strategic goal of informing nuclear public policy.
All applications and supporting documents are now due by 11:59 p.m. (EDT) on Monday, May 23.
Technical Session|Sponsored by RPD
Wednesday, June 16, 2021|1:15–3:00PM (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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