Fast Reactors and Accelerator Driven Systems Knowledge Base

IAEA-TECDOC--1172: Small power and heat generation systems on the basis of propulsion and innovative reactor technologies

Advisory group meeting on small power and heat generation systems on the basis of propulsion and innovative reactor technologies. Obninsk (Russian Federation) 20-24 Jul 1998

International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--1172

Abstract

In the future for developing regions and remote areas one or two power reactors in the 50 MW(e) to 100 MW(e) range could be appropriately applied for electricity and heat production. Introducing and managing such a small programme with conventional reactor systems would require a mature supporting technological infrastructure and many skilled and highly trained staff at the site, which might be a problem for some countries. An increased number of small conventional reactors (e.g. with on-site refuelling) would increase the burden and expenditure for assuring security and non-proliferation. To this end, the time has come to develop an innovative small reactor concept that meets the following requirements: reliable, safe operation with a minimum of maintenance and supporting infrastructure, economic competitiveness with alternative energy sources available to the candidate sites, and significant improvements in proliferation resistance relative to existing reactor systems.

This meeting, which included participants from ten countries (Canada, China, Egypt, France, India, Indonesia, Japan, the Republic of Korea, the Russian Federation and the United States of America) brought together a group of international experts to review and assess the propulsion reactor design features and operational experience, mode of its alternative application, as well as to discuss the systems approach and requirements for innovative small reactors and rationale for selecting them.

view the full text of this conference report (format: PDF, size= 14827kB, 196 pages)

see also:

Articles

Operational experience with propulsion nuclear plants
Polunichev, V. (OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation))

A multi-purpose reactor
Changwen Ma (Institute of Nuclear Energy Technology, Tsinghua University Beijing, Beijing (China))

Basic safety principles of KLT-40C reactor plants
Beliaev, V.; Polunichev, V. (OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation))

A floating desalination/co-generation system using the KLT-40 reactor and Canadian RO desalination technology
Humphries, J.R.; Davies, K. (Candesal Enterprises Ltd., Ottawa (Canada))

Implementation of the project for the construction and operation of a nuclear heat and power plant on the basis of a floating power unit with KLT-40C reactors
Polushkin, A.K.; Kuzin, E.A. (JSC Malaya Energetika, Moscow (Russian Federation)); Vorobiov, V.M. (JSC Atomenergo, St. Petersburg (Russian Federation)); Klykov, D.M. (JSC Iceberg, St. Petersburg (Russian Federation)); Panov, J.K. (OKBM, Nizhny Novgorod (Russian Federation))

The use of engineering features and schematic solutions of propulsion nuclear steam supply systems for floating nuclear power plant design
Achkasov, A.N.; Grechko, G.I.; Pepa, V.N.; Shishkin, V.A. (Research and Development Institute of Power Engineering, Moscow (Russian Federation)

Design features of SMART for barge mounted application
Doo-Jeong Lee; Ju-Hyeon Yoon; Ju-Pyung Kim; Jong-In Kim; Moon-Hee Chang (Korea Atomic Energy Research Institute, Taejon (Korea, Republic of))

Advanced marine reactor MRX and its application for electricity and heat co-generation
Ishida, T.; Ochiai, M. (Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken (Japan)); Hoshi, T. (Research Organization for Information Science and Technology, Tokai-mura, Naka-gun, Ibaraki-ken (Japan))

Civilian application of propulsion reactor in Indonesia
Djokolelono, M.; Arbie, B.; Lasman, A.N. (National Atomic Energy Agency (BATAN) (Indonesia))

New concepts for small power reactors without on-site refuelling for non-proliferation
Brown, N.W.; Hasberger, J.A. (Lawrence Livermore National Laboratory, Livermore, CA (United States))

Use of Russian technology of ship reactors with lead-bismuth coolant in nuclear power
Zrodnikov, A.V.; Chitaykin, V.I.; Gromov, B.F.; Grigoryv, O.G.; Dedoul, A.V.; Toshinsky, G.I. (Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation)); Dragunov, Yu.G.; Stepanov, V.S. (EDO 'Gidropress', Podoolsk, Moscow (Russian Federation))

Advanced 4S (super safe, small and simple) LMR
Minato, A. (Central Research Institute of Electric Power Industry, Tokyo (Japan)); Handa, N. (Toshiba Co-operation, Power Systems and Services Company, Yokohama (Japan))

Use of nuclear space technology of direct energy conversion for terrestrial application
Chitaykin, V.I.; Meleta, Ye.A.; Yarygin, V.I.; Mikheyev, A.S.; Tulin, S.M. (Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))

Development of a neutron therapy treatment complex
Zrodnikov, A.V.; Petrov, Eh.E.; Leonov, I.N.; Ivanov, E.A.; Khoromskij, V.A. (Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation)); Tcyb, A.F.; Mardynskij, Ju.S. (Medical Radiology Scientific Centre, Obninsk, Kaluga Region (Russian Federation))