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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
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.