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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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 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.
H. Jochem Rütten, Eberhard Teuchert
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 164-171
Technical Paper | Reactor | doi.org/10.13182/NT76-A31679
Articles are hosted by Taylor and Francis Online.
A favorable distribution of the fuel temperature in combination with a high cooling gas outlet temperature as necessary for a helium-turbine power plant can be achieved in a pebble-bed reactor with “once-through-then-out” fueling without leaving the scope of present feasibility. The equilibrium cycle is reached after a well-balanced and short running-in period. For non-base-load operation, the reactor can be controlled by moving the control rods in the upper void above the pebble bed. Withdrawing the rods causes an increase of the maximum fuel temperature by only 56°C. To avoid replacing of the side reflector during a time of 30 yr, the fast-neutron flux in the reflector can be remarkably lowered by inserting a certain amount of neutron poison into the reflector graphite and by an outer ring of “breeding” fuel elements, respectively.