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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 Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
S. Esnouf, A. Dannoux-Papin, E. Bossé, V. Roux-Serret, C. Chapuzet, F. Cochin, J. Blancher
Nuclear Technology | Volume 208 | Number 2 | February 2022 | Pages 347-356
Technical Paper | doi.org/10.1080/00295450.2021.1896927
Articles are hosted by Taylor and Francis Online.
The Alternative Energies and Atomic Energy Commission and Orano have developed a modeling tool named the Simulation Tool Of RAdiolysis Gas Emission (STORAGE) for assessing gas generation of intermediate-level waste. The first version of this model was designed to estimate gas (more specifically hydrogen) generation by radiolysis of organic materials contained in waste packages.
To verify the validity of the model, a series of measurements was performed on U, Pu–contaminated solid waste issued from the Orano plutonium laboratories at the MELOX facility. Twenty-one drums containing technological waste (gloves, bags, filters, metallic parts, etc.) packaged inside polyvinyl chloride sleeves were set up and hydrogen production was measured over a period of more than 1 year. Several levels of contamination and organic content were studied.
STORAGE calculations are conservative and most of the time in good agreement with experimental measurements with the uncertainties. As expected, the simplest cases (organic waste or filtering media) are well described by the model. The data are obviously more widely dispersed when the waste is composed of a mixture of organic materials and metal. Nevertheless, an understanding of the waste (package composition) allows a fairly precise description and ultimately a satisfactory estimation of the hydrogen production rate.