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Titre du document / Document title

Operating and test experience with EBR-II, the IFR prototype

Auteur(s) / Author(s)

SACKETT J. I. (1) ;

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

(1) Argonne National Laboratory, PO. Box 2528, Idaho Falls, Idaho 83403-2528, ETATS-UNIS

Résumé / Abstract

The Experimental Breeder Reactor number 2 (EBR-II) has operated for 30 years, the longest for any liquid metal cooled reactor (LMR) power plant in the world. Given the scope of what has been developed and demonstrated over those years, it is arguably the most successful test reactor operation ever. Tests have been carried out on virtually every fast reactor fuel type. The reactor itself has been extensively studied. The most dramatic safety tests, conducted on 3 April, 1986, showed that an LMR with metallic fuel could safely accommodate loss of flow or loss of heat-sink without scram. EBR-II operated as the Integral Fast Reactor (IFR) prototypes demonstrating important innovations in safety, plant design, fuel design and actinide recycle. The ability to accommodate anticipated transients without scram passively resulted in significant simplification of the reactor plant, primarily through less reliance on emergency power and not having to require the secondary sodium or steam systems to be safety grade. These features have been quantified in a probabilistic risk assessment (PRA) conducted for EBR-II, demonstrating considerable safety advantages over other reactor concepts. Fundamental to the superior safety and operating characteristics of this reactor is the metallic U-Pu-Zr alloy fuel. Performance of the fuel has been fully proven: achieved burnup levels exceed 20 at.% in the lead test assemblies. A complete set of fuel performance and safety limits has been developed and was carried forward in formal safety documents supporting conversion of the core to IFR fuel. The last major demonstration planned was to assess the performance of recycled actinides in the fuel and to confirm that passive safety characteristics are maintained with recycled actinide fuel in the core.

Revue / Journal Title

Progress in nuclear energy    ISSN  0149-1970 

Source / Source

1997, vol. 31, no 1-2 (226 p.)  (1 p.3/4), pp. 111-129

Langue / Language

Anglais

Editeur / Publisher

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

Mots-clés anglais / English Keywords

Nuclear reactor

;

Operating experience

;

Fast reactor

;

Fast breeder

;

Liquid metal

;

Nuclear safety

;

Plutonium Uranium Zirconium Alloys

;

Risk analysis

;

Probabilistic assessment

;

Service life

;

Nuclear fuel

;

Performance

;

Mots-clés français / French Keywords

Réacteur nucléaire

;

Expérience exploitation

;

Réacteur rapide

;

Surgénérateur rapide

;

Métal liquide

;

Sûreté nucléaire

;

Plutonium Uranium Zirconium Alliage

;

Analyse risque

;

Estimation probabiliste

;

Durée service

;

Combustible nucléaire

;

Performance

;

Mots-clés espagnols / Spanish Keywords

Reactor nuclear

;

Experiencia explotación

;

Reactor rápido

;

Reactor reproductor rápido

;

Metal líquido

;

Seguridad nuclear

;

Plutonio Uranio Zirconio Aleación

;

Análisis riesgo

;

Estimacíon probabilista

;

Duración servicio

;

Combustible nuclear

;

Rendimiento

;

Localisation / Location

INIST-CNRS, Cote INIST : 17686, 35400006135116.0060

Nº notice refdoc (ud4) : 2532990



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