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Division Spotlight
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.
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.
Leon Leenders, Udo Wehmann, Christopher Grove, Kevin Hesketh, Winfried Zwermann
Nuclear Science and Engineering | Volume 178 | Number 4 | December 2014 | Pages 509-523
Technical Paper | doi.org/10.13182/NSE14-15
Articles are hosted by Taylor and Francis Online.
The zero-power reactor VENUS (Vulcain Experimental Nuclear Study) was built in 1963–1964 at CEN-SCK, Mol, Belgium, as a nuclear mock-up of a projected spectral shift marine reactor called VULCAIN. The facility was modified in 1966 and 1967 in preparation for carrying out a series of critical experiments for the Belgian Plutonium Recycle Programme (PRP), which was partially supported by EURATOM. This was the VENUS-PRP program that took place between 1967 and 1975. VENUS-PRP-9 and VENUS-PRP-9/1, and VENUS-PRP-7 were two series of these PRP configurations that were carried out in 1967–1968 and that have recently been subject to evaluations as part of the Organisation for Economic Co-operation and Development, Nuclear Energy Agency International Reactor Physics Experiment Evaluation Project (IRPhEP). The VENUS-PRP-9 and VENUS-PRP-9/1 configurations focused on the study of the power distribution across the boundary between a standard UO2 fuel region, enriched to 4 wt% 235U, and a mixed oxide fuel region made of UO2, enriched to 3 wt% 235U with ∼1 wt% PuO2, simulating a one-cycle burnt fuel. The IRPhEP evaluation focused on evaluating reaction rates and powers measured along a line that crossed the boundary between the two regions. In the VENUS-PRP-7, VENUS-PRP-7/1, and VENUS-PRP-7/3 series—which used essentially the same fuel pins—reactivities, reactivity worths of substituted and removed fuel pins, and radial fission rate distributions were measured; these quantities were evaluated in the framework of the IRPhEP project.