References
- 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.
- 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.
- 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.
- 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.
- 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.
- 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.
- 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.
- 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.
- 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.
- 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.
- 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.
- E. Tomlinson, C. Brown, Nuclear criticality safety considerations in design of dry fuel assembly storage arrays, Nucl. Technol. 63 (1983) 347-350. https://doi.org/10.13182/NT83-A33293
- F. Brown, A Review of Best Practices for Monte Carlo Criticality Calculations, Los Alamos Natl. Lab., 2009, pp. 1-10. LA-UR-09-03136.
- R. Brewer, Criticality Calculations with MCNP5 TM : A Primer, Los Alamos Natl. Lab., 2009, pp. 0-201. LA-UR-09-00380.