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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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.