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References 1. International Energy Agency. (2008). Energy technology prospectives: Scenario 7 strategies to 2050 . Technical report. OECD/IEA, France. 2. Generation IV International Forum (GIF). (2014). Technology Roadmap Update for Generation IV Nuclear Energy Systems . OECD Nuclear Energy Agency. 3. Frima, L. L. W. (2013). Burnup in a molten salt fast reactor . Master Thesis. Department of Radiation Science and Technology, Faculty of Applied Sciences, Delft University of Technology. Available from https://d1rkab7tlqy5f1.cloudfront

NUKLEONIKA 2015;60(2):372 doi: 10.1515/nuka-2015-0038 ERRATUM M. Miglierini Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava, Slovakia and Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, V Holešovičkách 2, 180 00 Prague 8, Czech Republic, E-mail: Received: 18 June 2014 Accepted: 12 October 2014 Erratum to

References 1. Mihułek, M. (Ed.). (2003). Charakterystyka technologiczna rafi nerii ropy i gazu w Unii Europejskiej. Warsaw: Ministerstwo Środowiska. 2. Rada do Spraw Atomistyki. (2006). Strategia rozwoju atomistyki w Polsce. Warsaw: Państwowa Agencja Atomistyki. 3. Machaj, B., Jakowiuk, A., Świstowski, E., & Palige, J. (2011). Operation manual of Gamma Scanner. Warsaw: Institute of Nuclear Chemistry and Technology. 4. Krzanowski, W. J. (2000). Principles of multivariate analysis: A user’s perspective. Oxford University Press. 5. Rencher, A. C. (1997

:// . 4. International Atomic Energy Agency. (2007). Liquid metal cooled reactors: Experience in design and operation. Vienna: Nuclear Power Technology Development Section IAEA. (IAEA-TECDOC-1569). 5. International Atomic Energy Agency. (2006). Fast Reactor Database 2006 Update. Vienna: Nuclear Power Technology Development Section IAEA. (IAEA-TECDOC-1531). 6. U.S. DOE Nuclear Research Advisory Committee and the Generation IV International Forum. (2002). A Technology Roadmap for Generation IV Nuclear Energy Systems. 7. Westlen, D. (2007). Why faster is better


NUKLEONIKA 2017;62(4):243244 doi: 10.1515/nuka-2017-0035 EDITORIAL The IAEA has been fostering and facilitating the develop- ment and deployment of nuclear and radiation technology applications as important components to deliver specifi c benefi ts to the global society, as well as to address specifi c priority needs of its Member States (MS). In this context, the Scientifi c Forum of the IAEA General Conference held in 2015 on the topic of, ‘Atoms in Industry: Radiation Technology for Development’ showcased several such achievements and the vital role

Choppin was a gifted lecturer. During his 45-year career at FSU (he retired in 2001), he mentored more than 100 Ph.D. students and postdoctoral research associates. FSU recognized him in 1967 with distinction as a Robert O. Lawton Dis- tinguished Professor. Greg’s achievements were recognized through numerous awards and honors, including honorary doctorates from Loyola University New Orleans and from Chalmers University of Technology in Sweden, the Humboldt- -Stiftung U.S. Senior Scientist Award (1979), the Manufacturing Chemists Association National College

. Malczewski Faculty of Earth Sciences, University of Silesia, 60 Będzińska Str., 41-200 Sosnowiec, Poland, E-mail: A. Grabias Institute of Electronic Materials Technology, 133 Wolczyńska Str., 01-919 Warsaw, Poland Received: 30 August 2016 Accepted: 10 December 2016 © 2017 D. Malczewski et al. This is an open access article distributed under the Creative Commons Attribution -NonCommercial-NoDerivatives 3.0 License (CC BY-NC-ND 3.0).

irradiator in view of its use for calibration purposes. Radiat. Prot. Dosim., 141(2), 114-126. 8. McConn Jr, R. J., Gesh, C. J., Pagh, R. T., Rucker, R. A., & Williams III, R. G. (2011). Compendium of material composition data for radiation transport modeling - radiation portal monitor project. Washington: Pacifi c Northwest National Laboratory Richland. 9. Berthold Technologies. (1996). Neutron probe LB6411 - operating manual. Bad Wildbag, Germany. 10. Blizard, E. P., & Miller, J. M. (1958). Radiation attenuation characteristics of structural concrete. Oak Ridge: Oak

References 1. Park, J. J., Shin, J. M., Park, G. I., Lee, J. W., & Song, K. C. (2009). An advanced voloxidation process at KAERI. In Global 2009, 6-11 September (Paper 9196). Paris, France. 2. Lee, H., Park, G. I., Kang, K. H., Hur, J. M., Kim, J. G., Ahn, D. H., Cho, Y. Z., & Kim, E. H. (2011). Pyro-processing technology development at KAERI. Nucl. Eng. Technol., 43, 317-328. 3. Park, J. J., Park, C. J., Chun, J. I., Lee, J. W., Shin, J. M., Park, G. I., & Song, K. C. (2008). Evaluation of the effects of the advanced voloxidation process on pyro-processing. I

concepts. BARC Highlights - Reactor Technology and Engineering, from 8. Pelowitz, D. B. (2008). MCNPX2.6.0 user manual. Los Alamos: Los Alamos National Laboratory (LA- -CP-07-1473). 9. Thorium high temperature reactor (THTR), from 10. Fensin, M. L. (2008). Development of the MCNPX depletion capability: A Monte Carlo depletion method that automates the coupling between MCNPX and CINDER90 for high fi delity burn-up calculations. Doctoral dissertation, University of Florida. 11