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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
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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
December 2023
Nuclear Technology
Fusion Science and Technology
November 2023
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Argonne assists advanced reactor development with award-winning safety software
The development of modern nuclear reactor technologies relies heavily on complex software codes and computer simulations to support the design, construction, and testing of physical hardware systems. These tools allow for rigorous testing of theory and thorough verification of design under various use or transient power scenarios.
Technical Session|Sponsored by RPD
Thursday, December 2, 2021|3:05–4:50PM EST |Fairchild
Session Chair:
Zeyun Wu (VCU)
Alternate Chair:
Massimiliano Fratoni
Session Organizer:
Student Assistant:
Grace Stanke
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Verification of Medium-Wise Multi-Group Cross Section Calculation Capability of FRENDY/MG
3:10–3:30PM EST
Go Chiba (Hokkaido Univ.), Akio Yamamoto (Nagoya Univ.)
Summary
Reactivity Insertion Transient Analysis for C5G7-TD Benchmark with PANDAS-MOC
3:30–3:50PM EST
Shunjiang Tao (Purdue Univ.), Yunlin Xu (Purdue Univ.)
Bayesian Transposition: A Practical Approach Using Nuclear Reactor Start Up Data
3:50–4:10PM EST
Pamela A. Lopez (CNRS), Adrien Bidaud (CNRS)
Monte Carlo Simulation of Liquid Fuel Flow in Molten Salt Reactor in the iMC Code
4:10–4:30PM EST
HyeonTae Kim (KAIST), Yonghee Kim (KAIST)
Adaptive Mesh Refinement in Monte Carlo Neutron Simulations
4:30–4:50PM EST
Kristin Stolte (Texas A&M Univ.), Pavel Tsvetkov (Texas A&M Univ.)
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