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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Doonyapong Wongsawaeng, Donald Olander
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 279-291
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3876
Articles are hosted by Taylor and Francis Online.
A liquid metal (LM) consisting of one-third weight fraction each of Pb, Sn, and Bi has been investigated as the bonding substance in place of He in the pellet-cladding gap of light water reactor fuel elements. The LM bond eliminates the large T over the preclosure gap that is characteristic of helium-bonded fuel elements. Because the LM does not wet either UO2 or Zircaloy, simply loading fuel pellets into a cladding tube containing LM at atmospheric pressure leaves unfilled regions (voids) in the bond, which lead to local fuel hot spots. Voids were eliminated during fabrication by first evacuating the rod loaded with solid alloy and a fuel stack, melting the alloy, pushing down the fuel stack to drive the LM into the gap, and finally applying at least 5 atm He overpressure. Fabrication of a 4-m-long full-scale fuel rod using this technique was successfully demonstrated. A destructive examination revealed numerous breaks in the frozen alloy bond, but all of these appeared to result from handling the fuel rod. Application to commercial fuel manufacturing should require only minor modifications to existing fabrication lines. The most suitable nondestructive examination technique utilizes a collimated X-ray beam to probe edge-on the region between the pellet surface and the cladding inside diameter.