ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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
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
Zeyun Wu (VCU)
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Verification of Medium-Wise Multi-Group Cross Section Calculation Capability of FRENDY/MG
Go Chiba (Hokkaido Univ.), Akio Yamamoto (Nagoya Univ.)
Reactivity Insertion Transient Analysis for C5G7-TD Benchmark with PANDAS-MOC
Shunjiang Tao (Purdue Univ.), Yunlin Xu (Purdue Univ.)
Bayesian Transposition: A Practical Approach Using Nuclear Reactor Start Up Data
Pamela A. Lopez (CNRS), Adrien Bidaud (CNRS)
Monte Carlo Simulation of Liquid Fuel Flow in Molten Salt Reactor in the iMC Code
HyeonTae Kim (KAIST), Yonghee Kim (KAIST)
Adaptive Mesh Refinement in Monte Carlo Neutron Simulations
Kristin Stolte (Texas A&M Univ.), Pavel Tsvetkov (Texas A&M Univ.)
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