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Division Spotlight
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.
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
NWTRB to hold public meeting on SNF disposal and corrosion
The Nuclear Waste Technical Review Board, an independent federal agency that evaluates the Department of Energy’s efforts to manage and dispose of spent nuclear fuel and high-level radioactive waste, will hold a two-day public meeting May 21–22 to review information on the DOE’s research and development activities related to the disposal of SNF and HLW in crystalline host rocks and on the corrosion of commercial SNF after disposal.
Amir N. Nahavandi, Richard F. Von Hollen
Nuclear Science and Engineering | Volume 22 | Number 4 | August 1965 | Pages 463-469
Technical Paper | doi.org/10.13182/NSE65-A20633
Articles are hosted by Taylor and Francis Online.
An analytical model for the prediction of steam-water critical-flow pressure, mass discharge and pressure gradients in the approach region to critical flow is presented. The continuity, momentum and energy equations are applied to successive differential elements along the conduit and are solved numerically on an IBM-7094 digital computer for the maximum discharge flow rate. The proposed model assumes thermal equilibrium conditions and employs the modified Armand correlation to relate the void fraction to steam quality. The frictional losses in the momentum equation are obtained by two methods: a separated flow model and Armand model. A comparison of the analytical predictions with available test results on small diameter pipes shows that: 1) the present model agrees with the published test data; and 2) both frictional loss models are equally valid, and the selection of a particular method depends on the degree of conservatism desired.