NUMERICAL APPROACH FOR QUANTIFICATION OF SELFWASTAGE PHENOMENA IN SODIUM-COOLED FAST REACTOR
Sodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer heat from the reactor core. The main hazard associated with sodium is its rapid reaction with water. Sodium-water reaction (SWR) takes place when water or vapor leak into the sodium side through a crack on a...
Saved in:
Published in | Nuclear engineering and technology Vol. 47; no. 6; pp. 700 - 711 |
---|---|
Main Authors | , , , , , |
Format | Journal Article |
Language | Korean |
Published |
2015
|
Subjects | |
Online Access | Get full text |
Cover
Loading…
Be the first to leave a comment!