Analysis and insights about FE-calculations of the EC-forever-experiments

International Conference on Nuclear Engineering, Proceedings, ICONE

Volumn 1, Issue , 2002, Pages 595-601

  Willschuetz, H G ^a   Altstadt, E ^a   Weiss, F P ^a   Sehgal, B R ^a  

^a INSTITUTE OF ION BEAM PHYSICS AND MATERIALS RESEARCH   (Germany)

Author keywords

Advanced creep modelling; FEM calculations; Metallographic investigations; Scaled core melt down experiments; Vessel support as accident mitigation measure

Indexed keywords

ACCIDENT MITIGATION MEASURE; ADVANCED CREEP MODELING; REACTOR PIT; SCALED CORE MELTDOWN EXPERIMENTS; VESSEL SUPPORT;

ACCIDENT PREVENTION; COMPUTER SIMULATION; COOLING; CREEP; DECISION MAKING; FAILURE (MECHANICAL); FINITE ELEMENT METHOD; HEAT CONVECTION; OPTIMIZATION; PRESSURE EFFECTS; PRESSURE VESSELS;

CORE MELTDOWN;

EID: 0036387765     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/ICONE10-22262     Document Type: Conference Paper

References (6)

1. Altstadt, E., Moessner, Th., 2000, "Extension of the ANSYS® creep and damage simulation capabilities", Report, FZR-296, Forschungszentrum Rosendorf, Dresden, Germany
2. Ikonen, K., 1999, "Creep Model Fitting Derived from REVISA Creep, Tensile and Relaxation Measurements", Technical Report MOSES-4/99, VTT-Energy, Espoo, Finland.
3. Lemaitre, J., 1996, A Course on Damage Mechanics, ISBN 3-540-60980-6, 2nd edition Springer-Verlag Berlin, Heidelberg, New York.
4. Mueller, G., Böhmert J., 2000, Metallographic Post-Test Investigations for the scaled Core-Meltdown-Experiments FOREVER-1 and -2, Rossendorf, Report, FZR-298.
5. Sehgal, B.R., Nourgaliev, R.R., Dinh, T.N., Karbojian, A., 1999, "FOREVER experimental program on reactor pressure vessel creep behavior and core debris retention", Proceedings of the 15-th International Conference on Structural Mechanics in Reactor Technology (SMiRT-15), Seoul, Korea, August 15-20, 1999.
6. Willschuetz, H.-G., E. Altstadt, B.R. Sehgal, and F.-P. Weiss, 2001, "Coupled thermal structural analysis of LWR vessel creep failure experiments", NUCLEAR ENGINEERING AND DESIGN, vol 208, pp 265-282.