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M. Yamanaka
2. Yamanaka M, Pyeon CH (2019) Benchmarks of criticality in solid-moderated and solidreflected core in at Kyoto University Critical Assembly. Nucl Sci Eng 193:404
3. Fukushima M, Kitamura Y, Kugo T et al (2016) Benchmark models for criticalities of FCA-IX
assemblies with systematically changed neutron spectra. J Nucl Sci Technol 53:406
4. Goorley JT, James MR, Booth TE et al (2013) Initial MCNP6 release overview—MCNP6
version 1.0. LA-UR-13-22934
5. 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
6. 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
7. Okumura K, Kugo T, Kaneko K et al (2007) SRAC2006: a comprehensive neutronic calculation
code system. JAERI-Data/Code 2007-004
8. Yokoyama K, Hazama T, Numata K et al (2014) Development of comprehensive and versatile
framework for reactor analysis, MARBLE. Ann Nucl Energy 66:51
9. Fowler TB, Vondy DR (1969) Nuclear reactor core analysis code: Citation. ORNL-TM-2496,
rev. 2
10. Hara A, Takeda T, Kikuchi Y (1984) SAGEP: two-dimensional sensitivity analysis code based
on generalized perturbation theory. JAERI-M 84-027
11. Hazama T, Chiba G, Sugino K et al (2006) Development of fine and ultra-fine group cell
calculation code SLAROM-UF for fast reactor analysis. J Nucl Sci Technol 43:908
12. 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
13. Usachev LN (1964) Perturbation theory for the breeding ratio and for other number ratios
pertaining to various reactor processes. J Nucl Energy 18:571
14. Gandini A (1967) A generalized perturbation method for bi-linear functionals of the real and
adjoint neutron fluxes. J Nucl Energy 21:755
15. Cecchini GP, Salvatores M (1971) Advances in the generalized perturbation theory. Nucl Sci
Eng 46:304
16. Kobayashi K (1996) Reactor Physics. Corona Publishing Co. Ltd. Tokyo, Japan. [in Japanese]
17. Cacuci DG (2004) On the neutron kinetics and control of accelerator-driven systems. Nucl Sci
Eng 148:55
18. Broadhead BL, Rearden BT, Hopper CM et al (2004) Sensitivity- and uncertainty-based
criticality safety validation techniques. Nucl Sci Eng 146:340
19. 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
20. Dragt JB, Dekker JM, Grupperlaar H et al (1977) Methods of adjustment and error evaluation
of neutron capture cross sections; application to fission product nuclides. Nucl Sci Eng 62:117
21. Cacuci DG, Inoescu-bujor M (2010) Best-estimate model calibration and prediction through
experimental data assimilation: I. mathematical framework Nucl Sci Eng 165:18
22. Rearden BT, Jessee MA (2016) SCALE code system. ORNL/TM-2005/39 version 6.2.1
23. Nauchi Y, Kameyama T (2005) Proposal of direct calculation of kinetic parameters β eff and
based on continuous energy Monte Carlo method. J Nucl Sci Technol 42:503
24. Meulekamp RK, van der Marck SC (2006) Calculating the effective delayed neutron fraction
with Monte Carlo. Nucl Sci Eng 152:142
25. Rearden BT, Williams ML, Jessee MA et al (2011) Sensitivity and uncertainty analysis
capabilities and data in SCALE. Nucl Technol 174:236
26. Perfetti CM, Rearden BT (2016) Development of a generalized perturbation theory method for
sensitivity analysis using continuous-energy Monte Carlo methods. Nucl Sci Eng 182:354
27. OECD/NEA (2008) ICSBEP guide to the expression of uncertainties. https://www.oecd-nea.
org/science/wpncs/icsbep/documents/UncGuide.pdf, Accessed 30 June 2020
M. Yamanaka
2. Yamanaka M, Pyeon CH (2019) Benchmarks of criticality in solid-moderated and solidreflected core in at Kyoto University Critical Assembly. Nucl Sci Eng 193:404
3. Fukushima M, Kitamura Y, Kugo T et al (2016) Benchmark models for criticalities of FCA-IX
assemblies with systematically changed neutron spectra. J Nucl Sci Technol 53:406
4. Goorley JT, James MR, Booth TE et al (2013) Initial MCNP6 release overview—MCNP6
version 1.0. LA-UR-13-22934
5. 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
6. 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
7. Okumura K, Kugo T, Kaneko K et al (2007) SRAC2006: a comprehensive neutronic calculation
code system. JAERI-Data/Code 2007-004
8. Yokoyama K, Hazama T, Numata K et al (2014) Development of comprehensive and versatile
framework for reactor analysis, MARBLE. Ann Nucl Energy 66:51
9. Fowler TB, Vondy DR (1969) Nuclear reactor core analysis code: Citation. ORNL-TM-2496,
rev. 2
10. Hara A, Takeda T, Kikuchi Y (1984) SAGEP: two-dimensional sensitivity analysis code based
on generalized perturbation theory. JAERI-M 84-027
11. Hazama T, Chiba G, Sugino K et al (2006) Development of fine and ultra-fine group cell
calculation code SLAROM-UF for fast reactor analysis. J Nucl Sci Technol 43:908
12. 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
13. Usachev LN (1964) Perturbation theory for the breeding ratio and for other number ratios
pertaining to various reactor processes. J Nucl Energy 18:571
14. Gandini A (1967) A generalized perturbation method for bi-linear functionals of the real and
adjoint neutron fluxes. J Nucl Energy 21:755
15. Cecchini GP, Salvatores M (1971) Advances in the generalized perturbation theory. Nucl Sci
Eng 46:304
16. Kobayashi K (1996) Reactor Physics. Corona Publishing Co. Ltd. Tokyo, Japan. [in Japanese]
17. Cacuci DG (2004) On the neutron kinetics and control of accelerator-driven systems. Nucl Sci
Eng 148:55
18. Broadhead BL, Rearden BT, Hopper CM et al (2004) Sensitivity- and uncertainty-based
criticality safety validation techniques. Nucl Sci Eng 146:340
19. 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
20. Dragt JB, Dekker JM, Grupperlaar H et al (1977) Methods of adjustment and error evaluation
of neutron capture cross sections; application to fission product nuclides. Nucl Sci Eng 62:117
21. Cacuci DG, Inoescu-bujor M (2010) Best-estimate model calibration and prediction through
experimental data assimilation: I. mathematical framework Nucl Sci Eng 165:18
22. Rearden BT, Jessee MA (2016) SCALE code system. ORNL/TM-2005/39 version 6.2.1
23. Nauchi Y, Kameyama T (2005) Proposal of direct calculation of kinetic parameters β eff and
based on continuous energy Monte Carlo method. J Nucl Sci Technol 42:503
24. Meulekamp RK, van der Marck SC (2006) Calculating the effective delayed neutron fraction
with Monte Carlo. Nucl Sci Eng 152:142
25. Rearden BT, Williams ML, Jessee MA et al (2011) Sensitivity and uncertainty analysis
capabilities and data in SCALE. Nucl Technol 174:236
26. Perfetti CM, Rearden BT (2016) Development of a generalized perturbation theory method for
sensitivity analysis using continuous-energy Monte Carlo methods. Nucl Sci Eng 182:354
27. OECD/NEA (2008) ICSBEP guide to the expression of uncertainties. https://www.oecd-nea.
org/science/wpncs/icsbep/documents/UncGuide.pdf, Accessed 30 June 2020