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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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.
Mark W. Crump, John C. Lee
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 87-96
Technical Paper | Instrument | doi.org/10.13182/NT78-A32135
Articles are hosted by Taylor and Francis Online.
A mathematical model for ex-core detector response in pressurized water reactor (PWR) configurations is presented, based on the use of a spatial weighting function that is independent of core power distribution. The spatial weighting function is derived equivalently using a point kernel model and from numerical solutions of the adjoint neutron transport equation. These methods are verified through the use of experimental thermal flux data for deep penetration in water and metal media. An adjoint ANISN weighting function calculation for a one-dimensional cylindrical PWR model also shows good agreement with an equivalent point kernel calculation. Weighting function calculations using the point kernel method for a detailed three-dimensional model based on the Indian Point Unit 2 Reactor indicate that 91% of ex-core detector response is due to the five fuel assemblies nearest the detector. We believe that the weighting functions obtained with the point kernel method represent reliable information that can be used in the analysis of ex-core detector response during reactor operations.