Metallographical and numerical investigation of the EC-FOREVER-4 test

Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04

Volumn , Issue , 2004, Pages 1082-1089

  Willschuetz, H G ^a   Altstadt, E ^a   Mueller, G ^a   Sehgal, B R ^b   Boehmert, J ^a  

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

^b ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; FINITE ELEMENT METHOD; LIGHT WATER REACTORS; MATHEMATICAL MODELS; MICROSTRUCTURE; NUCLEAR ENERGY; RADIOISOTOPES; REACTOR CORES; THERMAL LOAD;

FINITE ELEMENT MODEL; HEAT GENERATION; MELT INJECTION ORIFICE; REACTOR PRESSURE VESSEL (RPV);

PRESSURE VESSELS;

EID: 14844291610     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (11)

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3. Giri, A., et al., EC-FOREVER Experiments on Thermal and Mechanical Behaviour of a Reactor Pressure Vessel during a Severe Accident Technical Report. EC-FOREVER-3(B) test. Stockholm, Sweden, 2002.
4. Ikonen, K., Creep Model Fitting Derived from REVISA Creep, Tensile and Relaxation Measurements, Report MOSES-4/99, VTT-Energy, Espoo, Finland, 1999.
5. Mongabure Ph., Creep Tests on LHF and OLHF SA533B1 Steel, Report SEMT/LISN/RT/00-060/A, CEA, France, 2000.
6. Sainte Catherine, C. Tensile and creep tests material characterization of pres-sure vessel steel (16MND5) at high temperatures (20 up to 1300°C). Rapport SEMT/LISN/RT/98-009/A, CEA, France, 1998 (experimental data files).
7. Sehgal, B.R., Nourgaliev, R.R., Dinh, T.N., and Karbojian, A., 1999. FOREVER experimental program on reactor pressure vessel creep behavior and core debris retention. In: Proceedings of the 15_th International Conference on Structural Mechanics in Reactor Technology (SMiRT_15), Seoul, South Korea, August 15-20, 1999.
8. B.R. Sehgal, et al., EC-FOREVER Experiments on Thermal and Mechanical Behaviour of a Reactor Pressure Vessel during a Severe Accident. Technical Report. EC-FOREVER-4 test. Stockholm, Sweden, 2002.
9. Willschütz, H.-G., E. Altstadt, B.R. Sehgal, and F.-P Weiss: Coupled thermal structural analysis of LWR vessel creep failure experiments, Nucl. Eng. Des., vol 208, pp 265-282, 2001.
10. Willschütz, H.-G, et al., Simulation of Creep Tests with French or German RPV-steel and investigation of a RPV-support against failure, ANNALS OF NUCLEAR ENERGY, vol 30, pp 1033-1063, 2003.
11. Willschuetz, H.-G., E. Altstadt, B.R. Sehgal, F.-P. Weiss, Post-Test Calculations of Medium Scaled Pressure Vessel Creep Failure Experiments Proceedings of ICAPP '03, Paper 3200, Córdoba, Spain, May 4-7, 2003.