Safety features of the PFBR
Prototype Fast Breeder Reactor (PFBR) is a 500 MWe pool type, sodium-cooled nuclear reactor, which is presently in an advanced stage of construction on the southeastern Indian coastline at Kalpakkam. India has chosen the closed fuel cycle option in view of its phased expansion of nuclear power gener...
Gespeichert in:
Veröffentlicht in: | Nuclear engineering international 2013-08, Vol.58 (709), p.32-35 |
---|---|
Hauptverfasser: | , |
Format: | Magazinearticle |
Sprache: | eng |
Schlagworte: | |
Online-Zugang: | Volltext |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
Zusammenfassung: | Prototype Fast Breeder Reactor (PFBR) is a 500 MWe pool type, sodium-cooled nuclear reactor, which is presently in an advanced stage of construction on the southeastern Indian coastline at Kalpakkam. India has chosen the closed fuel cycle option in view of its phased expansion of nuclear power generation extending through the latter stages of its programme, whereby the full energy potential of uranium and thorium can be exploited efficiently. In fast breeder reactors (FBRs), fission of plutonium-239 enables sizable and gainful conversion of around 70% fertile uranium-238 to fissile plutonium-239 and conversion of fertile thorium-232 to fissile uranium-233 in the radial blanket, which can provide adequate fissionable material to sustain the third stage Indian Nuclear Power Programme. Even though the venture is a prototype, the approach to the project is on par with construction of any commercial nuclear reactor. On completion, this reactor will not only produce 500 MWe power, but also pave the way for abundant power production using indigenous materials and technology and will open up the gateway for the country's future energy security. The primary objective of PFBR is to demonstrate the techno-economic viability of fast breeder reactors at an industrial scale. The fast breeder reactors would make effective utilization of depleted uranium available in the country, and use Plutonium as a fuel with significant reduction in radioactive waste. |
---|---|
ISSN: | 0029-5507 |