Accomplishments and challenges of the severe accident research

Nuclear Engineering and Design

Volumn 210, Issue 1-3, 2001, Pages 79-94

  Sehgal, B R ^a  

^a ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; CONTAINMENT VESSELS; LIGHT WATER REACTORS;

SEVERE ACCIDENT RESEARCH;

NUCLEAR REACTOR ACCIDENTS;

EID: 0035575433     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(01)00433-2     Document Type: Article

References (44)

1. The COMET-concept for cooling of ex-vessel corium melts
2. Latest findings of RASPLAV Project
3. First vapor explosion calculations performed with the MC3D code
4. High temperature hydrogen-air steam detonation experiments in the BNL small scale development apparatus
5. Analytical prediction of core heat up/liquefaction/slumping
6. Experimental simulation of core melt spreading on a LWR containment floor in a severe accident
7. Flame acceleration limits for nuclear safety applications
8. Severe accident recriticality analysis
9. On the importance of a strong coupling between physico-chemistry and thermalhydraulics for modelling late phases of severe accidents in LWRs
10. The cora-program: Out-of-pile experiments on severe fuel damage
11. Insight into steam explosions with corium melts in KROTOS
12. Verification of IVA5 computer code for melt-water interaction analysis
13. Experimental simulation of core melt spreading in two dimensions
14. An overview of the PHEBUS FPT1 results concerning the fission product release, transport and containment behavior
15. In-vessel retention of corium at the Loviisa Plant'
16. The PHEBUS FP program
17. The FARO programme recent results and synthesis
18. Corium melt quenching tests at low pressure and subcooled water in FARO
19. PBF severe fuel damage program: Results and comparison to analysis
20. Counterpart and replicate DCH experiments at two different physical scales
21. The WECHSEL-Mod2 Code: A computer program for the interaction of a core melt with concrete including the long term behavior
22. MACE project overview
23. Core melt pressure vessel interactions during a light water reactor severe accident (MVI Project)
24. Experiments and analyses of melt jet impingment during severe accidents
25. Heat transfer processes in reactor vessel lower plenum during late phase of in-vessel core melt progression
26. Integral experiments on in-vessel coolability and vessel creep: Results and analysis of the FOREVER-C1 test
27. Experimental investigation on melt spreading in one and two dimensions
28. Core Melt Pressure Vessel Interactions During a Light Water Reactor Severe Accident (MVI Project)
29. Reflooding experiments with LWR-type fuel rod simulators in the QUENCH facility
30. Results of recent NUPEC hydrogen related tests
31. An assessment of steam-explosion-induced containment failure
32. Reactor safety study
33. Hydrogen mixing experiments in the HDR containment under severe accident conditions