Characterization of heat transfer processes in a melt pool convection and vessel-creep experiment

Nuclear Engineering and Design

Volumn 211, Issue 2-3, 2002, Pages 173-187

  Sehgal, B R ^a   Nourgaliev, R R ^a   Dinh, T N ^a  

^a ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

Author keywords

[No Author keywords available]

Indexed keywords

CREEP; DATABASE SYSTEMS; DEFORMATION; ELECTRIC HEATING; HEAT FLUX; STEEL CONTAINERS;

MELT POOL CONVECTION;

HEAT TRANSFER;

EID: 0036467956     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(01)00434-4     Document Type: Article

References (28)

1. Effects of a hypothetical core melt accident on a PWR vessel with top-entry instrument
2. A finite element analysis of a pressurized containment vessel during core melt down
3. Finite element analyses of a BWR vessel and penetration under severe accident conditions
4. An assessment of the effects of heat flux distribution and penetration on the creep rupture of a reactor vessel lower head
5. Investigation of high-temperature strength of 15X2HMFA vessel steel in temperature range of 1000-1300 °C
6. Lower head creep-rupture sensitivity studies
7. Prediction of thermoplastic failure of a reactor pressure vessel under a postulated core melt accident
8. Failure modes of the BWR reactor vessel bottom head
9. Creep rupture behaviour of a PWR lower head in a core-melt accident
10. A time temperature relationship for rupture and creep stresses
11. Ermittlung von festigkeits- und verformungskennwerten des stahls 20MnMoNi55 von Raumtemperatur bis 900 °C
12. 12
13. Overview of NRC sponsored LWR lower head failure research program
14. Progress made in the area of reactor pressure vessel behaviour
15. FOREVER experiment on thermal and mechanical behavior of a reactor vessel during a severe accident
16. Integral experiments on in-vessel coolability and vessel creep: Results and analysis of the FOREVER-C1 test
17. FOREVER experimental program on reactor pressure vessel creep behavior and core debris retention
18. Creep rupture failure of reactor pressure vessel lower head during severe accidents
19. Comparison of thermal and mechanical responses of the Three Mile Island unit 2 reactor vessel
20. High-temperature creep and tensile data for pressure vessel steels SA533B1 and SA508-CL2
21. Local creep rupture failure modes on a corium-loaded lower head