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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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.
N. Prasad Kadambi, Roger W. Tilbrook
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 276-282
Technical Paper | Reactor | doi.org/10.13182/NT78-A32113
Articles are hosted by Taylor and Francis Online.
Boiling initiation in a liquid-metal fast breeder reactor (LMFBR) has in the past been assumed to lead inevitably to the potential for loss of coolable geometry. To ensure conservatism, it was necessary to preclude boiling under all accident conditions. Limited boiling in the radial blanket of the Clinch River Breeder Reactor due to a hypothetical major leak in the primary heat transport system is not likely to lead to assembly-wide dryout and cladding melting. A series of scoping calculations based on applicable physical processes has shown that (a) boiling is likely to be limited to only six subchannels, (b) flow reversal is unlikely, (c) there are ample heat sinks for condensation of sodium vapor, (d) film dryout is unlikely, and (e) cladding melting is unlikely. The consequences listed are of continuously decreasing likelihood, hence providing confidence that coolable geometry is not threatened by limited boiling in the radial blanket. This analysis was performed for a conventional LMFBR core arrangement.