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IAEA-TECDOC--466: Advanced fuel for fast breeder reactors: Fabrication and properties and their optimization

Technical committee meeting on advanced fuel for fast breeder reactors: Fabrication and properties and their optimization. Vienna (Austria). 3-5 Nov 1987

International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--466

Abstract

The present design for FBR fuel rods includes usually MOX fuel pellets cladded into stainless steel tubes, together with UO2 axial blanket and stainless steel hexagonal wrappers. Mixed carbide, nitride and metallic fuels have been tested as alternative fuels in test reactors. Among others, the objectives to develop these alternative fuels are to gain a high breeding ratio, short doubling time and high linear ratings. Fuel rod and assembly designers are now concentrating on finding the combination of optimized fuel, cladding and wrapper materials which could result in improvement of fuel operational reliability under high burnups and load-follow mode of operation. The purpose of the meeting was to review the experience of advanced FBR fuel fabrication technology, its properties before, under and after irradiation, peculiarities of the back-end of the nuclear fuel cycle, and to outline future trends. As a result of the panel discussion, the recommendations on future Agency activities in the area of advanced FBR fuels were developed. A separate abstract was prepared for each of the 10 presentations of this meeting.

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Articles

Status of (UPu)C and (UPu)N fuel development in BARC
Ganguly, C.; Hegde, P.V.; Sengupta, A.K. (Bhabha Atomic Research Centre, Bombay (India). Radiometallurgy Div.)

Fabrication of uranium-plutonium mixed nitride and thermally stable carbide fuels
Arai, Y.; Fukushima, S.; Shiozawa, K.; Handa, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan))

Quality control of uranium-plutonium mixed carbide and nitride fuels
Maeda, A.; Iwai, T.; Ohmichi, T.; Handa, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan))

Mixed nitride fuels fabrication in conventional oxide line
Bernard, H.; Bardelle, P.; Warin, D. (CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France))

Use of carbide-nitride fuel in the USSR. A review
Majorshin, A.A.; Zabud'ko, L.M.; Bibilashvilij, Yu.K.; Bogatyr, S.M. (Vsesoyuznyj Nauchno-Issledovatel'skij Inst. Neorganicheskikh Materialov, Moscow (USSR))

Fabrication processes and characterization of LMFBR carbide and nitride fuels and fuel pins
Richter, K.; Blank, H. (Commission of the European Communities, Karlsruhe (Germany, F.R.). European Inst. for Transuranium Elements)

Performance of He-bonded LMFBR carbide fuels at the beginning of life and consequences for their subsequent behaviour
Blank, H.; Campana, M.; Coquerelle, M.; Richter, K. (Commission of the European Communities, Karlsruhe (Germany, F.R.). European Inst. for Transuranium Elements)

Advanced fuel for fast breeder reactors produced by gelation methods
Alder, H.P.; Ledergerber, G.; Stratton, R.W. (Paul Scherrer Inst. (PSI), Wuerenlingen (Switzerland))

Performance of BOR-60 vibropack uranium-plutonium oxide fuel pins
Gadzhiev, G.I.; Majorshin, A.A.; Petukhov, A.A. (Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR))

Present status of FBR mixed oxide and advanced fuel development at PNC
Endo, H.; Nakajima, I. (Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan))