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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
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.