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Online training and education from the VR-1 reactor—Lessons learned
Novak Ondrej,Bily Tomas,Huml Ondrej,Sklenka Lubomir,Fejt Filip,Rataj Jan 한국원자력학회 2023 Nuclear Engineering and Technology Vol.55 No.12
Hands-on education and training is a key part of fixing and developing technology knowledge and is an inherent part of many engineering and scientific curricula. However, access to large complex training facilities, such as nuclear reactor, could be limited by various factors, such as unavailability of those facilities in the region, high traveling costs or harmonization of the schedules of hands-on E&T with theoretical lectures and with the operational schedule of the facility. To handle the issue, several success stories have been reached with the introduction of the Internet Reactor Labs (IRL). The Internet Reactor Labs can strongly contribute to accessibility of training at research reactors and can contribute to improvements in their utilization. The paper describes the development of the Internet Reactor Lab at the VR-1 reactor of the Czech Technical University in Prague. Contrary to single-purpose IRLs, it presents various modalities of online teaching and training in experimental reactor physics and reactor operation in general as well as outreach activities that have been developed in recent years
Copper neutron transport libraries validation by means of a <sup>252</sup>Cf standard neutron source
Schulc, Martin,Kostal, Michal,Novak, Evzen,Simon, Jan Korean Nuclear Society 2021 Nuclear Engineering and Technology Vol.53 No.10
Copper is an important structural material in various nuclear energy applications, therefore the correct knowledge of copper cross sections is crucial. The presented paper deals with a validation of different copper transport libraries by means of activation of selected samples. An intense <sup>252</sup>Cf(sf) source with a reference neutron spectrum was used as a neutron source. After irradiation, the samples were measured using a high purity germanium detector and the dosimeter reaction rates were inferred. These experimental data were compared with MCNP6 calculations using CENDL-3.1, JENDL-4.0, ENDF/B-VII.1, ENDF/B-VIII.0, JEFF-3.2 and JEFF-3.3 evaluated Cu transport libraries. The experiment specifically focuses on <sup>58</sup>Ni(n,p)<sup>58</sup>Co, <sup>93</sup>Nb(n,2n)<sup>92m</sup>Nb, <sup>197</sup>Au(n,g)<sup>198</sup>Au and <sup>55</sup>Mn(n,g)<sup>56</sup>Mn dosimetry reactions. Evaluated activation cross sections of these dosimetric reactions were taken from the IRDFF-II library. The best library performance depends on the energy region of interest.
Validation of the neutron lead transport for fusion applications
Martin Schulc,Michal Ko s 0 t al,Ev zen Novak,Tom a s Czakoj,Jan Simon 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.3
Lead is an important material, both for fusion or fission reactors. The cross sections of natural lead shouldbe validated because lead is a main component of lithium-lead modules suggested for fusion powerplants and it directly affects the crucial variable, tritium breeding ratio. The presented study discusses avalidation of the lead transport libraries by dint of the activation of carefully selected activation samples. The high emission standard 252Cf neutron source was used as a neutron source for the presented validationexperiment. In the irradiation setup, the samples were placed behind 5 and 10 cm of the leadmaterial. Samples were measured using a gamma spectrometry to infer the reaction rate and comparedwith MCNP6 calculations using ENDF/B-VIII.0 lead cross sections. The experiment used validated IRDFF-IIdosimetric reactions to validate lead cross sections, namely 197Au(n, 2n)196Au, 58Ni(n,p)58Co, 93Nb(n,2n)92mNb, 115In(n,n')115mIn, 115In(n,g)116mIn, 197Au(n,g)198Au and 63Cu(n,g)64Cu reactions. The thresholdreactions agree reasonably with calculations; however, the experimental data suggests a higher thermalneutron flux behind lead bricks. The paper also suggests 252Cf isotropic source as a valuable tool forvalidation of some cross-sections important for fusion applications, i.e. reactions on structural materials,e.g. Cu, Pb, etc.
Development of Multilayered Nanocomposites for Applications in Personal Protection
Jana Novotna,Vijay Baheti,Blanka Tomkova,Jiri Militky,Jan Novak 한국섬유공학회 2018 Fibers and polymers Vol.19 No.6
The aim of the presented research was to study the influence of surface layer material on improvement of impact, dielectric, EMI shielding and sound absorption properties of sandwich composites. The sandwich composite structure consisted of Kevlar or Carbon woven fabric at the surface layer, recycled high loft nonwoven in the center and a mixture of carbon particles/epoxy matrix as a binder to hold the surface layer and core together. The carbon particles were incorporated in epoxy in order to improve failure mechanism and enhance dielectric properties or electromagnetic shielding of sandwich composites. The biggest improvements on impact properties of sandwich composites were obtained when Kevlar fabric was used as surface layer. However, surface layer of carbon fabric was found to provide better dielectric properties and improve EMI shielding of sandwich composites against Kevlar fabric surface layer.