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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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
BWXT announces nuclear manufacturing plant expansion
BWX Technologies announced today plans to expand and add advanced manufacturing equipment to its manufacturing plant in Cambridge, Ontario, Canada.
A $36.3 million USD ($50M CAD) expansion will increase the plant’s size by 25 percent—to 280,000 square feet—and another $21.7 million USD ($30M CAD) will be spent on new equipment to increase and accelerate its output of large nuclear components. The investment will increase capacity and create more than 200 long-term jobs for skilled workers, engineers, and support staff, according to the company.
Ralph O. Meyer
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 293-311
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3763
Articles are hosted by Taylor and Francis Online.
In late 1993 and early 1994, tests in France and Japan showed that cladding damage in fuel rods with burnups above 50 GWd/ton occurs at much lower energies than in unirradiated fuel rods when exposed to large power pulses. During the last decade, significant additional test results have become available to permit an interim assessment of potential cladding failure in reactivity-initiated accidents (RIAs) in reactors with fuel burnups above 40 GWd/ton, which is generally regarded as high-burnup fuel. These data are summarized, and systematic biases due to atypical test conditions are identified. The magnitude of biases in the fuel enthalpy for failure are estimated to range from -19 to +27 cal/g for the cases analyzed. With these adjustments, a lower bound of the enthalpies for experimentally observed cladding failure is compared with potential enthalpies in pressurized water reactors and boiling water reactors. Based on available information on control rod worths, it is concluded that current operating reactors in the United States are not likely to experience cladding failure during the worst postulated RIAs.