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.
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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
Lotfi A. Belblidia, Gerardo M. Grandi, Christian Jönsson
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 325-336
Technical Paper | doi.org/10.13182/NSE04-A2461
Articles are hosted by Taylor and Francis Online.
This paper discusses the model and results for the Peach Bottom 2 Turbine Trip Test 2 using Studsvik Scandpower's transient code SIMULATE-3K. All data pertaining to core, vessel, and scenario were taken from the NEA/OECD BWR benchmark specifications. Nuclear data were generated with Studsvik Scandpower's lattice code CASMO-4 and core analysis code SIMULATE-3. Comparisons to measured data, sensitivity to model options and data, as well as results from more limiting scenarios are presented. SIMULATE-3K captures well the pressure wave propagation, void collapse during the pressurization phase, and resulting power excursion.
