Fast Reactors and Accelerator Driven Systems Knowledge Base

IAEA-TECDOC--916: Advanced fuels with reduced actinide generation.

Advanced fuels with reduced actinide generation.Technical committee meeting, Vienna (Austria). 21-23 Nov 1995

International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--916

Abstract

Nuclear energy can play an important future role in supplying the world population with energy. However, this form of energy will be successful only under certain conditions: it must meet very strict safety requirements, it must be economically competitive, and it must be acceptable to the public. Nuclear power produces radioactive wastes and in several countries the public raises concern about safety. Much development work on advanced nuclear power systems is going on in several countries, with participation of both governmental and private industries to meet these conditions. In the framework of this IAEA activity the Technical Committee Meeting on Advanced Fuels with Reduced Actinide Generation was organized. The aim of the meeting was to highlight current research activities and to identify new research areas and fields of possible co-operation. The scope of the meeting included advanced fuels for all types of nuclear reactors: light water reactors, heavy water reactors, high temperature reactors, fast reactors, molten salt reactors and for accelerator driven systems. Other topics covered a wide range of investigations made, or to be made in the Member States.

view the full text of this conference report (format: PDF, size= 9215kB, 189 pages)

see also:

Articles

Emerging applications of advanced fuels for energy generation and transmutation. Overview of IAEA activities
Pong Eil Juhn; Arkhipov, V. (International Atomic Energy Agency, Vienna (Austria))

Status of the nuclear fuel cycle in IAEA member states
Grigoriev, A. (International Atomic Energy Agency, Vienna (Austria))

Criteria for achieving actinide reduction goals
Liljenzin, J.O. (Calmers Univ. of Technology, Goeteborg (Sweden). Dept. of Nuclear Chemistry)

The feasibility of MA transmutation in CEFR
Zhang Yushan; Yi Xiaoyi; Su Lixin (Academia Sinica, Beijing, BJ (China). Inst. of Atomic Energy)

Liquid fuel concept benefits
Hron, M. (Nuclear Research Inst., Rez (Czech Republic))

Long term potential risk due to thorium mining
Schapira, J.P.; Menard, S. (Institut de Physique Nucleaire, Orsay (France))

Use of plutonium in pebble bed HTR's in a two ball type concept
Khoroshev, M.; Teuchert, E. (Forschungszentrum Juelich GmbH (Germany))

Reduction requirements for actinides with special regard to the isolation time at final disposal
Philippen, P.W. (Institute for Safety Research and Reactor Technology, Juelich (Germany))

Build-up of plutonium isotopes in HTR fuel elements. Comparison between computed prediction and chemical analysis
Werner, H. (Institute for Safety Research and Reactor Technology, Juelich (Germany). Research Center Juelich)

MOX fuels for reduced actinide generation
Anantharaman, K.; Krishnani, P.D.; Purandare, H.D.; Purushotham, D.S.C. (Bhabha Atomic Research Centre, Bombay (India))

Thorium fuel-cycle development through plutonium incineration by THORIMS-NES (Thorium Molten-Salt nuclear energy synergetics)
Furukawa, K. (Tokai Univ., Kanagawa (Japan). Inst. of Research and Development); Mitachi, K. (Toyohashi Univ. of Technology, Toyohashi (Japan). Dept. of Energy Engineering); Lecocq, A. (European Association for Molten-Salt Reactors Development, Orsay (France)); Furuhashi, A. (Nuclear Material Control Center, Tokyo (Japan)); Chigrinov, S.E. (Radiation Physics and Chemical Problems Inst., Minsk (Belarus))

A study for optimal transmutation system
Park, W.S.; Song, T.Y.; Shin, H.S.; Park, C.K. (Korea Atomic Energy Reserach Inst., Taejon (Korea, Republic of))

A partitioning-free transmutation concept of nuclear waste reduction
Taczanowski, S. (University of Mining and Metallurgy, Cracow (Poland). Faculty of Physics and Nuclear Techniques)

Some results on development, irradiation and post-irradiation examinations of fuels for fast reactor-actinide burner (MOX and inert matrix fuel)
Poplavsky, V.; Zabudko, L.; Moseev, L.; Rogozkin, B.; Kurina, I. (Institute of Physics and Power Engineering, Obninsk (Russian Federation))

A strategy for Pu destruction in PWRs
Magill, J.; Peerani, P.; Matzke, H.; Geel, J. van (European Commission, Karlsruhe (Germany). Inst. for Transuranium Elements)

Studies of HTGR Th-U fuel cycle at the Institute of Nuclear Energy Technology, Tsinghua University
Zhu Yongjin (Tsinghua Univ., Beijing (China). Inst. of Nuclear Energy Technology)

Neutronic analysis of a U-Th fuel cycle, lead cooled accelerator-driven system
Landeyro, P.A.; Guidotti, M. (ENEA, Rome (Italy))