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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.
Hiroshi Tochihara, Eiji Ochiai, Tadashi Hasegawa
Nuclear Technology | Volume 58 | Number 2 | August 1982 | Pages 310-317
Technical Paper | Analyse | doi.org/10.13182/NT82-A32939
Articles are hosted by Taylor and Francis Online.
The ex-core detector response in pressurized water reactors (PWRs) depends on not only power level but also core power distribution. Therefore, it is important to precisely calculate the assembly-wise spatial weighting factors for the ex-core detectors. Usually these factors are calculated with the one-dimensional transport code and point kernel calculational method, in which the neutron scattering effect outside of reactor vessel is neglected. But when the scattering effect is estimated to be rather big, we calculate the assembly-wise spatial weighting factors using the two-dimensional transport code, which includes the scattering effect. Consequently, we found that the weighting factors of peripheral assemblies that are remote from the detector but close to reactor vessel are rather big in comparison with the previous results. When we calculate the detector response during one control rod insertion test of three-loop PWR core using these weighting factors, the agreement between calculation and measurement is very good. A simple point kernel calculational method developed instead of the two-dimensional transport calculation that consumes much computer time.