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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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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
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.
Giacomo G. M. Cojazzi, Guido Renda, Jor Shan Choi, Jim Hassberger
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 76-90
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT179-76
Articles are hosted by Taylor and Francis Online.
The Generation IV International Forum (GIF) Proliferation Resistance and Physical Protection (PR&PP) Working Group has developed a methodology for the PR&PP evaluation of advanced nuclear energy systems (NESs). A notional sodium-cooled fast neutron nuclear reactor system, named the Example Sodium Fast Reactor (ESFR), was used as a case study for the development and demonstration of the GIF PR&PP evaluation methodology. This paper presents some of the results of the application of the GIF PR&PP evaluation methodology to a misuse scenario involving the ESFR. The ESFR baseline design and two design variations are addressed. Rather than presenting a complete evaluation of all the possible misuse scenarios, the paper concentrates on methodological aspects and illustrates how a qualitative analysis following the GIF PR&PP evaluation methodology can generate traceable results of the considered design variations and provide useful feedback for both system and safeguards designers as well.