Structural Integrity of Reactor Pressure Vessel for Small Break Loss of Coolant Accident

Cited 5 time in webofscience Cited 0 time in scopus
  • Hit : 318
  • Download : 0
Plant-specific analyses of the typical pressurized water reactor in Korea are performed to assure the structural integrity of the reactor pressure vessel during transient, which is expected to initiate pressurized thermal shock event. The deterministic analysis is performed to determine the critical time interval in the transient during which mitigating action can be effective. Also, the failure probability is obtained by performing probabilistic fracture mechanics analysis. In addition, several sensitivity analyses are performed for warm prestressing, plastic zone correction, and simulation option to calculate fracture toughness etc. to assess its effect on the failure probability.
Publisher
ATOMIC ENERGY SOC JAPAN
Issue Date
2009-03
Language
English
Article Type
Article
Keywords

THERMAL-SHOCK

Citation

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.46, no.3, pp.310 - 315

ISSN
0022-3131
DOI
10.3327/jnst.46.310
URI
http://hdl.handle.net/10203/100567
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 5 items in WoS Click to see citing articles in records_button

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0