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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Victor Ontiveros, Adrien Cartillier, Mohammad Modarres
Nuclear Science and Engineering | Volume 166 | Number 3 | November 2010 | Pages 179-201
Technical Paper | doi.org/10.13182/NSE10-05
Articles are hosted by Taylor and Francis Online.
Fire simulation codes are powerful tools for use in risk-informed and performance-based approaches for risk assessment. Following initial work performed in a joint effort between the U.S. Nuclear Regulatory Commission and the Electric Power Research Institute of a verification and validation of five popular fire simulation codes and research performed at the University of Maryland to quantify total code output uncertainty following a “black-box” approach, this research presents a “white-box” methodology with the goal of also accounting for uncertainties within a simulation code prediction. In this paper the white-box probabilistic approach is discussed to assess uncertainties associated with fire simulation codes. Uncertainties associated with the input variables to the codes as well as the uncertainties associated with the submodels and correlations used inside the code are accounted for. To validate code output calculations, experimental tests may also be available to compare against code calculations. These experimental results may also be used in the assessment of the code uncertainties. Building upon earlier research on model uncertainty performed at the University of Maryland, the methodology employed to estimate the uncertainties is based on a Bayesian estimation approach. This Bayesian estimation approach integrates all evidence available to arrive at an estimate of the uncertainties associated with a reality of interest being estimated by the simulation code. Examples of applications with results of the associated uncertainties are discussed in this paper.