This book offers a comprehensive overview of the reprocessing of spent nuclear fuels, and discusses the applications of radiation, particularly spallation neutrons and gamma rays. The unspent nuclear fuel of a reactor amounts to roughly 95 per cent of the loaded fuel. It contains both fertile and fissile fuels, minor and higher actinides and radioactive fission products. In 2015, out of approximately 4 million metric tons of spent fuel, only 90,000 metric tons was reprocessed worldwide; the rest was either sent to repositories, kept for cooling down, or put on a waiting list for future reprocessing. With regard to the direct reutilization of spent nuclear fuel, the new technique of 'Energy Amplifiers' has attracted considerable attention among the nuclear energy community. Presenting extensive information on this technique, the book is divided into eight major sections: (i) spent nuclear fuel and alternative transmutation methods, (ii) general concept of accelerator-driven subcritical systems (ADSS), (iii) spallation neutron sources and the possibility of incineration, (iv) requirements for nuclear data, (v) transmutation of spent nuclear fuel and extension of the fuel cycle, (vi) spallation neutron production facilities, (vii) major experimental facilities for ADSS, and (viii) software tools for the design and modelling of ADSS. The book is ideally suited as a textbook for graduate students as well as a reference guide for researchers and practitioners.
Dr Vinod Kumar Verma was a Professor of Physics at the University of Rajasthan, Jaipur (India) until April 2010 and a Professor of Engineering Physics/Nano Science at GGSIP University, New Delhi until January 2016. In a research career spanning more than 40 years he participated in international collaborations like EMU01, L3, WA93, WA98, GAMMA-2 & 3, E+T & QUINTA at the JINR, Dubna. He has authored or co-authored over 180 research papers and edited the proceedings of the Workshop on Physics of Accelerator Driven Sub-critical Systems (ADSS). In India, he is best known for his pioneering research on ‘spallation neutrons’ in the course of several S&T projects completed for the DST and DAE (Government of India). He has also successfully completed developmental work on two Monte Carlo Codes for the ADSS technology, i.e. the CASCADE 2004 version in collaboration with the JINR (Dubna) and the JA-IPU code for radiation damage with a team of Indian researchers. Over the past 20 years, he has initiated scientific collaborations with teams in the Czech Republic, S. Korea and Russia on the activity related to ADSS technique.
Dr. Karel Katovský graduated with a degree in nuclear engineering. His PhD thesis at the Faculty of Nuclear Sciences and Physical Engineering of the Czech Technical University in Prague (2008) was on experimental research and the nuclear data problems of ADSS. He subsequently spent several years at the Joint Institute for Nuclear Research (JINR) in Dubna. He worked at the Computation Reactor Physics Department of SKODA JS, where he dealt with nuclear fuel loading patterns and their optimization. Since 2012 he has been working as an Assistant Professor of Nuclear Engineering at Brno University of Technology, where he serves as a leader of the Nuclear Power Group to teach nuclear energy. He is the author or co-author of 37 SCOPUS-indexed papers, more than 50 conference papers, and about 30 research reports. He is a member of the Board of the Czech Nuclear Society and of the expert committee for nuclear energy of regional NGO associations in the NPP Dukovany area.
