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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.
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.
Jim P. Wei
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 44-52
Technical Paper | Reactor | doi.org/10.13182/NT79-A32378
Articles are hosted by Taylor and Francis Online.
A simplified interassembly heat transfer model has been developed to satisfy liquid-metal fast breeder reactor core restraint system analysis needs that explicitly treats steady-state intra-assembly and interassembly heat transfer in core assemblies. The intra-assembly heat transfer inside reactor assemblies is modeled based on application of the subchannel concept together with the use of bulk parameters for coolant velocity and coolant temperature within a subchannel. The model utilizes a tri-grid system to treat interassembly heat transfer between assemblies. Because of this special nodal scheme, a set of finite difference equations, derived from the energy equation for all the subchannels, duct wall, and gap flow, is actually a rather special system of simultaneous linear algebraic equations which have a tri-diagonal matrix form. Due to this special form, an efficient method of solution for computers is used without matrix elimination and inversion. Although this model was developed for core restraint applications, it is also well suited for the determination of core-wide coolant temperature distributions.