An assessment methodology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs

Cited 10 time in webofscience Cited 0 time in scopus
  • Hit : 192
  • Download : 0
A consistent probabilistic approach is proposed to evaluate the feasibility of in-vessel retention of the molten corium through external reactor vessel cooling (IVR-ERVC) during severe accidents of pressurized water reactors (PWRs). By combining the results of Level-1 probabilistic safety assessment, a critical heat flux correlation, and wall heat flux distributions calculated by a severe accident code with appropriate adjustment, we can reasonably predict the overall success probability of the IVR-ERVC from the viewpoint of thermal failure. The practicability of the proposed approach is illustrated with a preliminary application to the Korean Standard Nuclear Power Plant. This paper also discusses future developmental needs for more reliable assessment.
Publisher
PERGAMON-ELSEVIER SCIENCE LTD
Issue Date
2001-08
Language
English
Article Type
Article
Keywords

COOLABILITY; PRESSURE

Citation

ANNALS OF NUCLEAR ENERGY, v.28, no.12, pp.1237 - 1250

ISSN
0306-4549
DOI
10.1016/S0306-4549(00)00121-3
URI
http://hdl.handle.net/10203/240999
Appears in Collection
NE-Journal Papers(저널논문)
Files in This Item
There are no files associated with this item.
This item is cited by other documents in WoS
⊙ Detail Information in WoSⓡ Click to see webofscience_button
⊙ Cited 10 items in WoS Click to see citing articles in records_button

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0