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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.
C. Carrapiço, E. Berthoumieux, I. F. Gonçalves, F. Gunsing, A. Mengoni, P. Vaz, V. Vlachoudis, The n_TOF Collaboration
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 837-842
MC Calculations | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Radiation Measurements and Instrumentation | doi.org/10.13182/NT09-A9315
Articles are hosted by Taylor and Francis Online.
The n_TOF facility is a time-of-flight (TOF) spectrometer dedicated to studying neutron-induced reactions, mainly neutron capture and fission cross sections. The spectrometer consists of a pulsed proton beam (7 × 1012 protons/pulse, 6-ns width, 20 GeV/c) impinging on an 80 × 80 × 60 cm3 lead target. The neutrons produced by spallation reactions reach the detector station at 185 m through an evacuated tube. There, neutron-induced reactions are studied by using the TOF technique. The facility is unique for its high instantaneous neutron flux (of the order 106 neutrons/cm2 per proton pulse at 185 m), an excellent energy resolution, low background conditions, and a very low duty cycle. This combination allows one to measure neutron capture and fission cross sections in the energy range from 1 eV to 250 MeV with high precision.For the analysis of the data in the resolved resonance region up 1 MeV, a precise and accurate knowledge of the distribution of the energy resolution is mandatory. The only way to obtain the resolution function in a detailed way is to use Monte Carlo simulations together with the experimental verification with well-known resonance reactions at selected energies. Such calculations and an analytical fit of the results have been performed for the target setup of the first phase of data taking.Monte Carlo simulations performed for the assessment and comparison of the resolution function for different target configurations are reported. The different resolution functions are compared and discussed.