ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Terrestrial Energy looks at EnergySolutions-owned sites for IMSR plants
Advanced reactor developer Terrestrial Energy and Utah-based waste management company EnergySolutions announced they have signed a memorandum of understanding to collaborate on the siting and deployment of Terrestrial Energy’s integral molten salt reactor plants at EnergySolutions-owned sites.
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.