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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
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.
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Wednesday, June 15, 2022|1:00–2:45PM PDT|Redondo
Session Chair:
Nolan Goth
Alternate Chair:
Sheng Zhang
Session Organizer:
W. David Pointer
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Scaled Experiment Design for Transient Heat Transfer in Molten Salt-Cooled Reactor Channels
Omar Ashraf Alzaabi (Univ. California, Berkeley), Per Peterson (Univ. California, Berkeley)
Paper
Numerical Investigations on Hydrodynamic Molten Salt Lubricated Bearings
Yuqi Liu (Univ. New Mexico), Daniel L. Barth (High Temperature System Designs), Adam Burak (Univ. Michigan), Shuai Che (Univ. Michigan), Minghui Chen (Univ. New Mexico)
Design of a High-Temperature Molten-Salt Pump Bearing Test Facility
CFD Analysis of Tritium Removal from Molten Salt Reactors by Sparging Helium Gas Bubbles
Anthony G. Bowers Jr. (Univ. Massachusetts, Lowell), Subash L. Sharma (Univ. Massachusetts, Lowell), Piyush Sabharwall (INL)
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