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The human factor in licensing and operating the next generation of nuclear plants
As human factors specialists working at the intersection of human performance and nuclear operations, we are witnessing one of the nuclear sector’s most significant transitions in decades. The emergence of small modular reactors, microreactors, and other advanced designs is reshaping the industry’s landscape. Digital instrumentation and controls, passive safety systems, and increased automation are creating opportunities for greater safety margins and more flexible operation. These same features also fundamentally redefine what it means to “operate” a nuclear plant. Interactions among human roles, automation, and passive systems shape how people maintain awareness, exercise judgment, and intervene when necessary. These developments affect both operational realities and the regulatory foundations on which nuclear safety is built.
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.