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Titre du document / Document title

Fusion-driven transmutation of selected long-lived fission products

Auteur(s) / Author(s)

TAKIBAYEV A. (1) ; SAITO M. (1) ; ARTISYUK V. (2) ; SAGARA H. (1) ;

Affiliation(s) du ou des auteurs / Author(s) Affiliation(s)

(1) Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology 2-12-1 O-okayama, Meguro-ku, Tokyo 152-8550, JAPON
(2) Obninsk State Technical University for Nuclear Power Engineering (INPE) Studgorodok 1, Obninsk, Kaluga region, 249030, RUSSIE, FEDERATION DE

Résumé / Abstract

The long-term radiological burden associated with nuclear power production is usually attributed to long-lived fission products (LLFP). Their lifetime and large equilibrium mass and hence radioactivity accumulated in the course of fission energy generation make their storage a rather formidable task to solve. Therefore the idea of artificial incineration of LLFP through their transmutation has been quite naturally incorporated into the concept of self-consistent nuclear energy system (SCNES) based primarily on fast breeder reactor technologies. However it is now acknowledged that neutron environment of fission facilities including fast breeder reactors does not seem most appropriate for LLFP transmutation. The issue has been then extensively developed within the framework of multi-component self-consistent nuclear energy system (MCSCNES). Neutrons of specific quality required for LLFP transmutation are proposed there to be of non-fission origin. Given neutron excess available and neutron quality, a fusion neutron source (FNS) is appearing as the candidate No.1 to consider for LLFP transmutation. Research on LLFP transmutation by means of FNS has very long history and has received an additional boost during the decade passed. In the present study, potential of thermal flux blanket of FNS is exemplified by transmutation of 93Zr and 126Sn, the most difficult LLFP to transmute. It is shown that transmutation of 93Zr is effective even with a rather modest neutron loading of 1 MWt.m-2, typical for ITER project. Transmutation of 126 Sn, however, requires neutron loading of as high as 3 MWt.m-2 for DD fusion and is quite unattractive for DT fusion. In the latter case, transmutation through the threshold (n,2n) reaction may be preferable.

Revue / Journal Title

Progress in nuclear energy    ISSN  0149-1970 

Source / Source

Congrès
COE-INES International Symposium No1, Tokyo , JAPON (31/10/2004)
2005, vol. 47, no 1-4 (714 p.)  [Document : 7 p.] (11 ref.), pp. 354-360 [7 page(s) (article)]

Langue / Language

Anglais

Editeur / Publisher

Elsevier, Kidlington, ROYAUME-UNI  (1977) (Revue)

Mots-clés anglais / English Keywords

Tin 126

;

Zirconium 93

;

Neutron source

;

Waste management

;

Nuclear fusion

;

Transmutation

;

Fission product

;

Radioactive waste

;

Mots-clés français / French Keywords

Etain 126

;

Zirconium 93

;

Source neutron

;

Gestion déchet

;

Fusion nucléaire

;

Transmutation

;

Produit fission

;

Déchet radioactif

;

Mots-clés espagnols / Spanish Keywords

Fuente neutrón

;

Tratamiento desperdicios

;

Fusión nuclear

;

Transmutación

;

Producto fisión

;

Residuos radioactivos

;

Mots-clés d'auteur / Author Keywords

Transmutation

;

Fission products

;

Fusion neutron source

;

Localisation / Location

INIST-CNRS, Cote INIST : 17686, 35400013242863.0360

Nº notice refdoc (ud4) : 17035603



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