212
C. H. Pyeon
and the calculations by MCNP6.1 with JENDL-4.0 revealed the importance of the
effect of criticality bias on the precision of numerical simulations.
Sensitivity and uncertainty analyses of Pb isotope cross sections were conducted
with the combined use of sample reactivity experiments carried out at KUCA and
numerical simulations by the SRAC2006 and MARBLE code systems. The experimental sample reactivity was compared with the calculated one by the deterministic
approach with the covariance data of JENDL-4.0 as follows: A series of sensitivity and uncertainty analyses demonstrated the reliability of Pb isotope crosssection data of JENDL-4.0, such as the uncertainty of the covariance data, compared
with JENDL-3.3, ENDF/B-VII.0 and JEFF-3.1 libraries. Additionally, the numerical
results revealed the applicability of sensitivity and uncertainty analyses to the thermal
neutron spectrum cores, such as the KUCA core, demonstrating the improvement of
calculation results induced by the cross-section adjustment.
For the Bi isotope, sensitivity coefficients of the Bi isotope were relatively small
with the comparison of
27 Al,
235 U and
238 U comprising of fuel plates and core
components. Uncertainty induced by Bi cross sections demonstrated a reasonable
result of the Bi sample reactivity worth. From the results of Bi isotope uncertainty,
the comparative study on Bi and Pb sample reactivity worth was instrumental in
emphasizing the neutronics and the impact of Pb–Bi coolant material in ADS.
References
1. Pyeon CH, Fujimoto A, Sugawara T et al (2016) Validation of Pb nuclear data by Monte Carlo
analyses of sample reactivity experiments at Kyoto University Critical Assembly. J Nucl Sci
Technol 53:602
2. Pyeon CH, Fujimoto A, Sugawara T et al (2017) Sensitivity and uncertainty analyses of lead
sample reactivity experiments at Kyoto University Critical Assembly. Nucl Sci Eng 185:460
3. Pyeon CH, Yamanaka M, Oizumi A et al (2018) Experimental analyses of bismuth sample
reactivity worth at Kyoto University Critical Assembly. J Nucl Sci Technol 55:1324
4. Tsujimoto K, Sasa T, Nishihara K et al (2004) Neutronics design for lead-bismuth cooled
accelerator-driven system for transmutation of minor actinide. J Nucl Sci Technol 41:21
5. Goorley JT, James MR, Booth TE et al (2013) Initial MCNP6 release overview—MCNP6
version 1.0. LA-UR-13-22934
6. Shibata K, Iwamoto O, Nakagawa T et al (2011) JENDL-4.0: a new library for nuclear science
and technology. J Nucl Sci Technol 48:1
7. Shibata K, Kawano T, Nakagawa T et al (2002) Japanese evaluated nuclear data library version
3 revision-3: JENDL-3.3. J Nucl Sci Technol 39:1125
8. Chadwick MB, Oblozinsky P, Herman M et al (2006) ENDF/V-II.0: next generation evaluated
nuclear data library for nuclear science and technology. Nucl Data Sheet 107:2931
9. Koning A, Forrest R, Kellett M et al (2006) The JEFF-3.1 nuclear data library—JEFF report
21, OECD/NEA No. 6190
10. Iwamoto H, Nishihara K, Sugawara T et al (2013) Sensitivity and uncertainty analysis for an
accelerator-driven system with JENDL-4.0. J Nucl Sci Technol 50:856
11. Tsiboulia A, Khomyakov Y, Koscheev V et al (2002) Validation of nuclear data for Pb and Bi
using critical experiments. J Nucl Sci Technol suppl 2:1010
12. Chiba G, Okumura K, Sugino K et al (2011) JENDL-4.0 benchmarking for fission reactor
applications. J Nucl Sci Technol 48:172
C. H. Pyeon
and the calculations by MCNP6.1 with JENDL-4.0 revealed the importance of the
effect of criticality bias on the precision of numerical simulations.
Sensitivity and uncertainty analyses of Pb isotope cross sections were conducted
with the combined use of sample reactivity experiments carried out at KUCA and
numerical simulations by the SRAC2006 and MARBLE code systems. The experimental sample reactivity was compared with the calculated one by the deterministic
approach with the covariance data of JENDL-4.0 as follows: A series of sensitivity and uncertainty analyses demonstrated the reliability of Pb isotope crosssection data of JENDL-4.0, such as the uncertainty of the covariance data, compared
with JENDL-3.3, ENDF/B-VII.0 and JEFF-3.1 libraries. Additionally, the numerical
results revealed the applicability of sensitivity and uncertainty analyses to the thermal
neutron spectrum cores, such as the KUCA core, demonstrating the improvement of
calculation results induced by the cross-section adjustment.
For the Bi isotope, sensitivity coefficients of the Bi isotope were relatively small
with the comparison of
27 Al,
235 U and
238 U comprising of fuel plates and core
components. Uncertainty induced by Bi cross sections demonstrated a reasonable
result of the Bi sample reactivity worth. From the results of Bi isotope uncertainty,
the comparative study on Bi and Pb sample reactivity worth was instrumental in
emphasizing the neutronics and the impact of Pb–Bi coolant material in ADS.
References
1. Pyeon CH, Fujimoto A, Sugawara T et al (2016) Validation of Pb nuclear data by Monte Carlo
analyses of sample reactivity experiments at Kyoto University Critical Assembly. J Nucl Sci
Technol 53:602
2. Pyeon CH, Fujimoto A, Sugawara T et al (2017) Sensitivity and uncertainty analyses of lead
sample reactivity experiments at Kyoto University Critical Assembly. Nucl Sci Eng 185:460
3. Pyeon CH, Yamanaka M, Oizumi A et al (2018) Experimental analyses of bismuth sample
reactivity worth at Kyoto University Critical Assembly. J Nucl Sci Technol 55:1324
4. Tsujimoto K, Sasa T, Nishihara K et al (2004) Neutronics design for lead-bismuth cooled
accelerator-driven system for transmutation of minor actinide. J Nucl Sci Technol 41:21
5. Goorley JT, James MR, Booth TE et al (2013) Initial MCNP6 release overview—MCNP6
version 1.0. LA-UR-13-22934
6. Shibata K, Iwamoto O, Nakagawa T et al (2011) JENDL-4.0: a new library for nuclear science
and technology. J Nucl Sci Technol 48:1
7. Shibata K, Kawano T, Nakagawa T et al (2002) Japanese evaluated nuclear data library version
3 revision-3: JENDL-3.3. J Nucl Sci Technol 39:1125
8. Chadwick MB, Oblozinsky P, Herman M et al (2006) ENDF/V-II.0: next generation evaluated
nuclear data library for nuclear science and technology. Nucl Data Sheet 107:2931
9. Koning A, Forrest R, Kellett M et al (2006) The JEFF-3.1 nuclear data library—JEFF report
21, OECD/NEA No. 6190
10. Iwamoto H, Nishihara K, Sugawara T et al (2013) Sensitivity and uncertainty analysis for an
accelerator-driven system with JENDL-4.0. J Nucl Sci Technol 50:856
11. Tsiboulia A, Khomyakov Y, Koscheev V et al (2002) Validation of nuclear data for Pb and Bi
using critical experiments. J Nucl Sci Technol suppl 2:1010
12. Chiba G, Okumura K, Sugino K et al (2011) JENDL-4.0 benchmarking for fission reactor
applications. J Nucl Sci Technol 48:172