Monte Carlo simulations of criticality safety assessments of transuranic element storage in a pyroprocess facility |
Kim, Jinhwan
(Dept. of Nuclear & Quantum Engineering, Korea Advanced Institute of Science and Technology)
Kim, Jisoo (Dept. of Nuclear & Quantum Engineering, Korea Advanced Institute of Science and Technology) Lim, Kyung Taek (Dept. of Nuclear & Quantum Engineering, Korea Advanced Institute of Science and Technology) Ahn, Seong Kyu (Korea Atomic Energy Research Institute, KAERI) Park, Se Hwan (Korea Atomic Energy Research Institute, KAERI) Cho, Gyuseong (Dept. of Nuclear & Quantum Engineering, Korea Advanced Institute of Science and Technology) |
1 | H.D. Kim, H.S. Shin, D.Y. Song, T.H. Lee, B.Y. Han, S.K. Ahn, S.H. Park, Application of Safeguards-by-design for the Pyroprocessing Facilities in ROK, XL, 2012, pp. 24-31. |
2 | R.A. Borrelli, Use of curium spontaneous fission neutrons for safeguardability of remotely-handled nuclear facilities: fuel fabrication in pyroprocessing, Nucl. Eng. Des. 260 (2013) 64-77, https://doi.org/10.1016/j.nucengdes. 2013.03.025. DOI |
3 | R.A. Borrelli, Use of curium neutron flux from head-end pyroprocessing subsystems for the high reliability safeguards methodology, Nucl. Eng. Des. 277 (2014) 166-172, https://doi.org/10.1016/j.nucengdes.2014.06.028. DOI |
4 | R.A. Borrelli, Functional components for a design strategy: hot cell shielding in the high reliability safeguards methodology, Nucl. Eng. Des. 305 (2016) 18-27, https://doi.org/10.1016/j.nucengdes.2016.05.010. DOI |
5 | S.I. Moon, S.J. Seo, W.M. Chong, G.S. You, J.H. Ku, H.D. Kim, Identification of safety controls for engineering-scale pyroprocess facility, Nucl. Eng. Technol. 47 (2015) 915-923, https://doi.org/10.1016/j.net.2015.08.005. DOI |
6 | V. Barkauskas, R. Plukiene, A. Plukis, Actinide-only and full burn-up credit in criticality assessment of RBMK-1500 spent nuclear fuel storage cask using axial burn-up profile, Nucl. Eng. Des. 307 (2016) 197-204, https://doi.org/ 10.1016/j.nucengdes.2016.07.012. DOI |
7 | J.J. Herrero, A. Vasiliev, M. Pecchia, H. Ferroukhi, S. Caruso, Review calculations for the OECD/NEA burn-up credit criticality safety benchmark, Ann. Nucl. Energy 87 (2016) 48-57, https://doi.org/10.1016/j.anucene.2015.08.014. DOI |
8 | M. Rezaeian, J. Kamali, Effect of a dual-purpose cask payload increment of spent fuel assemblies from VVER 1000 Bushehr nuclear power plant on basket criticality, Appl. Radiat. Isot. 119 (2017) 80-85, https://doi.org/10.1016/ j.apradiso.2016.10.008. DOI |
9 | S.I. Moon, W.M. Chong, G.S. You, J.H. Ku, H.D. Kim, Y.K. Lim, H.S. Chang, Preliminary safety study of engineering-scale pyroprocess facility, Nucl. Eng. Technol. 46 (2014) 63-72, https://doi.org/10.5516/NET.06.2013.018. DOI |
10 | S.M. Bowman, I.C. Gauld, OrigenArp primer : How to Perform Isotopic Depletion and Decay Calculations with SCALE/ORIGEN, Oak Ridge Natl. Lab., 2010, pp. 1-85. ORNL/TM-20. |
11 | E. Tomlinson, C. Brown, Nuclear criticality safety considerations in design of dry fuel assembly storage arrays, Nucl. Technol. 63 (1983) 347-350. DOI |
12 | F. Brown, A Review of Best Practices for Monte Carlo Criticality Calculations, Los Alamos Natl. Lab., 2009, pp. 1-10. LA-UR-09-03136. |
13 | R. Brewer, Criticality Calculations with MCNP5 TM : A Primer, Los Alamos Natl. Lab., 2009, pp. 0-201. LA-UR-09-00380. |
14 | A. Mohammadi, M. Hassanzadeh, M. Gharib, Shielding calculation and criticality safety analysis of spent fuel transportation cask in research reactors, Appl. Radiat. Isot 108 (2016) 129-132, https://doi.org/10.1016/ j.apradiso.2015.12.045. DOI |
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