Challenges left in the area of in-vessel melt retention

Nuclear Engineering and Design

Volumn 209, Issue 1-3, 2001, Pages 87-96

  Asmolov, V ^a   Ponomarev Stepnoy, N N ^b   Strizhov, V ^b   Sehgal, B R ^c  

^a KURCHATOV INSTITUTE   (Russian Federation)

^b NUCLEAR SAFETY INSTITUTE   (Russian Federation)

^c ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

Author keywords

[No Author keywords available]

Indexed keywords

COOLING; NUCLEAR REACTORS; PRESSURE VESSELS; THERMAL CONDUCTIVITY; THERMAL LOAD;

MELT RETENTION;

NUCLEAR POWER PLANTS;

EID: 0035499143     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(01)00391-0     Document Type: Article

References (30)

1. Natural convection heat transfer in volumetrically heated spherical pools
2. Experimental study of heat transfer in the slotted channels at CTF facility
3. Large scale experiments for core melt retention
4. Experimental investigations of natural convection in spherical segments of volumetrically heated pools
5. In-vessel retention for the AP600 design during severe accidents
6. Experimental data on heat flux distribution from a volumetrically heated pools with frozen boundaries
7. Cooling of core debris within the reactor vessel lower head
8. Identification and assessment of BWR in-vessel accident management strategies
9. Essential experimental results of the CORA test program on severe code damage phenomena
10. Overview of severe accident research and SONATA-IV phase-I experiment at KAERI
11. Critical heat flux on thick walls of large, naturally convecting loops
12. Heat flux distribution from a volumetrically heated pool with high Rayleigh number
13. Corium melt quenching tests at low pressure and subcooled water in FARO
14. Reactor vessel external cooling for corium retention SULTAN experimental program and modeling with CATHARE, OECD/CSNI
15. Applicability of PHEBUS FP results to severe accident safety evaluations and management measures
16. SIMECO experiments on in-vessel melt pool formation and heat transfer with and without a metallic layer
17. FOREVER experimental program in reactor pressure vessel creep behavior and core debris retention
18. Core melt pressure vessel interactions during a light water reactor severe accident (MVI)
19. Experience from the first two integrated approaches to in-vessel retention through external cooling
20. Critical heat flux through curved, downward facing, thick walls
21. In-vessel coolability and retention of a core melt
22. The first results from the ACOPO experiments
23. A consistent approach to severe accident management
24. Experimental investigation on dryout heat flux of a particle debris bed with a downcomer