ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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 will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Siegfried Malang, Klaus Rust
Nuclear Technology | Volume 58 | Number 1 | July 1982 | Pages 53-62
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32957
Articles are hosted by Taylor and Francis Online.
For the investigation of thermohydraulic behavior during loss-of-coolant accidents (LOCAs), the nuclear fuel rods are simulated, in out-of-pile experiments, by electrically heated rods. These heater rods are required to produce temperature and heat flux histories at each position of the heater rod surface, identical to those of the nuclear fuel rods. Generally, these requirements are approximated by preprogramming of the transient heater rod power using estimated cooling conditions. However, the cooling conditions are not known very accurately prior to a test since the investigation of the thermohydraulics is the main purpose of the test. The use of an on-line process computer that controls the power of the heater rod by feedback of the measured cladding temperature to simulate, more closely, a LOCA has been suggested. A computer code simulating experiments in which the heater rod power is controlled by an on-line computer has been developed for checking and has demonstrated the validity of the method. In addition, the method has been confirmed by experiments performed at the Semiscale Test Facility.