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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Experimenters get access to NSUF facilities for irradiation effects studies
The Department of Energy’s Office of Nuclear Energy announced the recipients of “first call” 2025 Nuclear Science User Facilities (NSUF) Rapid Turnaround Experiment (RTE) awards on June 26. The 23 proposals selected from industry, national laboratories, and universities will receive a total of about $1.4 million. While each project is led by a different principal investigator, some call the same organization home. A total of 17 companies, labs, and universities are represented.
Aya Diab, Michael Corradini, Carl Martin
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 114-125
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A9356
Articles are hosted by Taylor and Francis Online.
Pressurized heavy water reactors of the CANDU design may be susceptible to a partial or a complete blockage of the flow of coolant to some of the pressure tubes. This event, although very rare, would result from the presence of debris in the heat transport conduits. In the case of an extreme event where the coolant flow is blocked completely, in addition to failure to scram the reactor, an accident scenario may prevail. Coolant trapped in the pressure tube is expected to boil off; the fuel rods would overheat and partially melt with the melt accumulating at the bottom of the pressure tube. This degraded situation, along with the high pressure involved under normal operation conditions, would lead to a rupture of the pressure tube. The pressure signature at the rupture site predicted from a lumped parameter phenomenological model is used as an input to a three-dimensional ANSYS model to assess the pressure signature at the inner walls of the tank in response to the pressure tube rupture. The pressure predicted by the ANSYS model is benchmarked against experimental data from the literature.