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
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
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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Vincent Hedberg, Mikhail Morev, Marco Silari, Zuzana Zajacová
Nuclear Technology | Volume 173 | Number 3 | March 2011 | Pages 327-331
Technical Note | Radiation Measurements and Instrumentation | doi.org/10.13182/NT11-A11666
Articles are hosted by Taylor and Francis Online.
Predictions of high-energy hadron activation of liquid argon in the calorimeter of A Thoroidal LHC ApparatuS (ATLAS) were carried out by folding particle flux spectra with the radionuclide production cross sections. Calculations were performed with a wide array of input data. Six sets of cross sections were folded with two sets of particle flux spectra, and the results were compared. The particle fluxes were obtained from simulations with the Monte Carlo radiation transport codes FLUKA and GCALOR. The cross-section sets were calculated according to the Rudstam and the Silberberg-Tsao formulas; taken from the Japanese Evaluated Nuclear Data Library (JENDL) and the Medium Energy Nuclear Data Library (MENDL); obtained from the Large Hadron Collider air activation studies; and compiled from various, predominantly experimental, sources.