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- 저자 : Czakoj, Tomas (검색결과 3 건)
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Comprehensive validation of silicon cross sections
Czakoj, Tomas,Kostal, Michal,Simon, Jan,Soltes, Jaroslav,Marecek, Martin,Capote, Roberto Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.12
Silicon, especially silicon in the form of SiO<sub>2</sub>, is a major component of rocks. Final spent fuel storages, which are being designed, are located in suitable rock formations in the Earth's crust. Reduction of the uncertainty of silicon neutron scattering and capture is needed; improved silicon evaluations have been recently produced by the ORNL/IAEA collaboration within the INDEN project. This paper deals with the nuclear data validation of that evaluation performed at the LR-0 reactor by means of critical experiments and measurement of reaction rates. Large amounts of silicon were used both as pure crystalline silicon and SiO<sub>2</sub> sand. The critical moderator level was measured for various core configurations. Reaction rates were determined in the largest core configuration. Simulations of the experimental setup were performed using the MCNP6.2 code. The obtained results show the improvement in silicon cross-sections in the INDEN evaluations compared to existing evaluations in major libraries. The new Thermal Scattering Law for SiO<sub>2</sub> published in ENDF/B-VIII.0 additionally reduces the discrepancy between calculation and experiments. However, an unphysical peak is visible in the neutron spectrum in SiO<sub>2</sub> obtained by calculation with the new Thermal Scattering Law.
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Calculation and measurement of Al prompt capture gammas above water in a pool-type reactor
Czakoj Tomáš,Košťál Michal,Losa Evžen,Matěj Zdeněk,Šimon Jan,Mravec Filip,Cvachovec František 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.10
Prompt capture gammas are an important part of the fission reactor gamma field. Because some of the structural materials after neutron capture can emit photons with high energies forming the dominant component of the gamma spectrum in the high energy region, the following study of the high energy capture gamma was carried out. High energy gamma radiation may play a major role in areas of the radiation sciences as reactor dosimetry. The HPGe measurements and calculations of the high-energy aluminum capture gamma were performed at two moderator levels in the VR-1 pool-type reactor. The result comparison for nominal levels was within two sigma uncertainties for the major 7.724 MeV peak. A larger discrepancy of 60% was found for the 7.693 MeV peak. The spectra were also measured using a stilbene detector, and a good agreement between HPGe and stilbene was observed. This confirms the validity of stilbene measurements of gamma flux. Additionally, agreement of the wide peak measurement in 7e9.2 MeV by stilbene detector shows the possibility of using the organic scintillators as an independent power monitor. This fact is valid in these reactor types because power is proportional to the thermal neutron flux, which is also proportional to the production of capture gammas forming the wide peak
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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.
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