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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Industry experts discuss nuclear’s role in powering data centers, meeting climate goals
As a primer to the American Nuclear Society Winter Conference and Expo, ANS Executive Director/Chief Executive Craig Piercy hosted a panel discussion titled “The State of Nuclear,” sponsored by the ANS Trustees of Nuclear. The October 29 discussion, the first in a two-part series, featured five thought leaders from the nuclear community as they reviewed the current state of nuclear power. The second panel took place during the ANS Winter Conference in Orlando, Fla., on November 18.
Paul R. Miles, Jared A. Cook, Zoey V. Angers, Christopher J. Swenson, Brian C. Kiedrowski, John Mattingly, Ralph C. Smith
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 37-53
Technical Paper | doi.org/10.1080/00295450.2020.1738796
Articles are hosted by Taylor and Francis Online.
Recent research has focused on the development of surrogate models for radiation source localization in a simulated urban domain. We employ the Monte Carlo N-Particle (MCNP) code to provide high-fidelity simulations of radiation transport within an urban domain. The model is constructed to employ a source location () as input and return the estimated count rate for a set of specified detector locations. Because MCNP simulations are computationally expensive, we develop efficient and accurate surrogate models of the detector responses. We construct surrogate models using Gaussian processes and neural networks that we train and verify using the MCNP simulations. The trained surrogate models provide an efficient framework for Bayesian inference and experimental design. We employ Delayed Rejection Adaptive Metropolis (DRAM), a Markov Chain Monte Carlo algorithm, to infer the location and intensity of an unknown source. The DRAM results yield a posterior probability distribution for the source’s location conditioned on the observed detector count rates. The posterior distribution exhibits regions of high and low probability within the simulated environment identifying potential source locations. In this manner, we can quantify the source location to within at least one of these regions of high probability in the considered cases. Employing these methods, we are able to reduce the space of potential source locations by at least 60%.