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Division Spotlight
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.
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.
Carroll B. Mills
Nuclear Technology | Volume 10 | Number 2 | February 1971 | Pages 133-138
Technical Paper and Note | Reactor | doi.org/10.13182/NT71-A30921
Articles are hosted by Taylor and Francis Online.
Requirements for underseas nuclear reactor power systems for small vessels include: simplified small reactor and plant control and instrumentation; long-term compatibility of fuel, structure, and coolant; and extended fuel lifetime, safety, and low cost. Neutronic qualities that reflect these requirements are: lowest critical mass for low cost and small size; low fuel concentration in the fuel elements consistent with extended fuel lifetime, small fuel effects on fuel element materials properties, and small fission-product effects; negative temperature and core geometry coefficients of reactivity, in the interest of minimizing safety and control problems, 100-g fuel burnup (100 MWd of energy). A reactor design that has these qualities uses a pressurized water moderated, beryllium (4-in.) reflected, solid fuel geometry with 0.070 g/ml 235U in the core, and zirconium fuel elements, with a fuel mass including 0.1 kg for burnup of under 0.8 kg 235U. This reactor core is 8 in. long and 8 in. in diameter, and contains 85%, by volume, of water at an operating temperature around 500°F, for a power level of 300 kW(th).