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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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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Latest News
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
Michael P. Manahan, Sr., Hassan S. Basha
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 389-398
Technical Paper | Material | doi.org/10.13182/NT91-A34533
Articles are hosted by Taylor and Francis Online.
The conventional approach to flux determination is to use high-purity dosimeters to characterize the neutron field. An alternative approach referred to as the material scrapings method is presented. Steel scrapings are cut from an in-service component and this material is used to measure the specific activity for various reactions. This approach enables the determination of the neutron flux and fluence incident on any component for which small chips of material can be safely obtained. The scrapings methodology was benchmarked by comparison with the results obtained using conventional dosimetry data from the San Onofre Nuclear Generation Station Unit 2. Pseudo fast fluxes (E 1.0 and 0.1 MeV) are cal culated by combining the surveillance capsule dosimetry measured activities with the corresponding effective cross sections. The effective cross sections for the reactions of interest are calculated using the analytically determined neutron spectrum at the surveillance capsule position. After the evaluation and testing of the surveillance capsule were completed, scrapings were taken from a broken Charpy specimen. The pseudo fluxes for the 54Fe(n,p)54Mn and 58Ni(n,p)58Co reactions were calculated using the same cross sections as those used for the capsule dosimetry analysis. The pseudo fluxes determined using the scrapings dosimetry are within 5% of the corresponding surveillance capsule pseudo fluxes.