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.
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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
Savannah River facility prepped for NNSA project
Work has begun to prepare the Savannah River Plutonium Processing Facility (SRPPF) at the Department of Energy’s Savannah River Site in South Carolina for its future national security mission: the manufacturing of plutonium pits for the National Nuclear Security Administration.
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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