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

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자료유형: 학술저널

저자정보: Martin Schulc (Research Centre Rez Ltd) Michal Ko s 0 t al (Research Centre Rez Ltd) Ev zen Novak (Research Centre Rez Ltd) Tom a s Czakoj (Research Centre Rez Ltd) Jan Simon (Research Centre Rez Ltd)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제54권 제3호

발행연도: 2022.3

수록면: 959 - 964 (6page)

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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.

#Lead cross sections #252Cf #ENDF/B-VIII.0 #Tritium breeding ratio #Lithium-lead modules #IRDFF-II

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