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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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!
Latest Magazine Issues
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
MURR expansion set back by Mo. state legislature
Spirits were high last month when a ribbon cutting was held at the University of Missouri for a $20 million, three-story, 47,000-square-foot addition, dubbed MURR West, to the MURR research reactor facilities.
Technical Session
Monday, May 16, 2022|10:15AM–12:00PM EDT|Fountainview
Session Chair:
Brendan M. Kochunas (Univ. Michigan)
Alternate Chair:
Nicolas E. Stauff (ANL)
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Transient Analysis of a Micro-Reactor Using the DireWolf Code Suite
Nathan Roskoff (Westinghouse Electric Co.), Vefa Kucukboyaci (Westinghouse Electric Co.), Alex Levinsky (Westinghouse Electric Co.), Vincent Laboure (INL), Jackson Harter (INL), Adam Zabriskie (INL), Lise Charlot (INL)
Paper
XE-100 Modeling and Simulation for Neutronic Analysis in MCNP6.2
Austin Carter (INL), Travis Lange (INL), Paolo Balestra (INL), Gerhard Strydom (INL), Sonat Sen (X-Energy), Raymond Wang (X-Energy)
Multiphysics Analysis System for Heat Pipe Cooled Micro Reactors Employing PRAGMA-OpenFOAM-ANLHTP
Jaeuk Im (Seoul Nat'l Univ.), Myung Jin Jeong (Seoul Nat'l Univ.), Namjae Choi (Seoul Nat'l Univ.), Kyung Min Kim (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.), Hyoung Kyu Cho (Seoul Nat'l Univ.)
Stability Margin Analysis of the Holos-Quad Microreactor Design
Shai Kinast (Nuclear Research Center Negev), Claudio Filippone (HolosGen), Brendan Kochunas (Univ. Michigan)
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