Berthold Technologies, B. (2020). Lb 1236 umo ii universal monitor, https://www.berthold.com. Berthold Technologies.
Campbell, L. W., Smith, L. E., and Misner, A. C. (2011). High-energy delayed gamma spectroscopy for spent nuclear fuel assay. IEEE Transactions on Nuclear Science, 58(1):231–240.
Fensin, M. L. (2008). Development of the MCNPX depletion capability: A Monte Carlo linked depletion method that automates the coupling between MCNPX and CINDER90 for high fidelity burnup calculations. University of Florida.
Ko, J.-H., Park, J.-H., Jung, I.-S., et al. (2014). Shielding analysis of dual purpose casks for spent nuclear fuel under normal storage conditions. Nuclear Engineering and Technology, 46(4):547–556.
Kralik, M., Kulich, V., and Studeny, J. (2000). Dosimetry at the interim spent fuel storage facility of the czech nuclear power plant dukovany. Journal of Nuclear Science and Technology, 37(sup1):762–766.
Kryuchkov, E., Opalovsky, V., and Tikhomirov, G. (2005). Modelling of radiation field around spent fuel container. Radiation Protection Dosimetry, 116(1-4):575–578.
Mirvakili, S., Keyvani, M., Arshi, S. S., et al. (2012). Possibility evaluation of eliminating the saturated control fuel element from Tehran research reactor core. Nuclear Engineering and Design, 248:197–205. NRC, U. et al. (1997). Standard review plan for dry cask storage systems. NUREG-1536.
Osifo, O. (2007). Automatic Gamma Scanning System for Measurement of Residual Heat in Nuclear Fuel. PhD thesis, Department of Neutron Research, Uppsala University.
Pelowitz, D. et al. (2013). MCNP6 Users Manual (Los Alamos National Laboratory). LACP-00634, May.
Qiu-kuan, W., Chang-hua, L., and Yan, Y. (2012). Advanced measuring (instrumentation) methods for nuclear installations: A Review. Science and Technology of Nuclear Installations, 2012.
Redus, R. (2002). Efficiency of Amptek XR-100T-CdTe and CZT Detectors Application Note ANCXT-1 Rev 2. CdTe/CZT Application Note, Amptek Inc., Bedford USA.