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RISS 인기검색어
- 검색키워드
- 저자 : Martin Schulc (검색결과 2 건)
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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.
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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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