Simulation of creep tests with French or German RPV-steel and investigation of a RPV-support against failure

Annals of Nuclear Energy

Volumn 30, Issue 10, 2003, Pages 1033-1063

  Willschutz H G ^a   Altstadt, E ^a   Sehgal, B R ^b   Weiss, F P ^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; CREEP TESTING; DATABASE SYSTEMS; FINITE ELEMENT METHOD; STEEL STRUCTURES; STRESS ANALYSIS;

REACTOR PRESSURE VESSELS (RPV);

PRESSURE VESSELS;

REINDEER PAPILLOMAVIRUS;

EID: 0037411204     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(03)00036-7     Document Type: Article

References (17)

1. Altstadt E., Moessner Th. Extension of the ANSYS® Creep and Damage Simulation Capabilities. Report, FZR-296. 2000;Forschungszentrum Rossendorf, Dresden, Germany.
2. ANSYS®, 2001. Programmer's Manual. ANSYS®, Inc.
3. Chu, T.Y., Pilch, M.M., Bentz, J.H., Ludwigsen, J.S., Lu, W.Y., Humphries L.L. 1999. Lower Head Failure Experiments and Analyses. Report, NUREG/CR-5582, SAND98-2047. Sandia National Laboratories, Albuquerque, NM, USA.
4. Kadner, M., 2001. Prüfbericht Nr. A191/1, Chemical Analysis of a Steel Specimen. Dresden, Germany.
5. Ikonen K. Creep Model Fitting Derived from REVISA Creep, Tensile and Relaxation Measurements. Technical Report MOSES-4/99. 1999;VTT-Energy, Espoo, Finland.
6. Lemaitre J. A Course on Damage Mechanics. 2nd edition:1996;Springer-Verlag, Berlin, Heidelberg, New York.
7. Mongabure Ph., Desmet M. RUPTHER Test#14 - Rupture Test at 1000 °C and Variable Pressure 8 then 6 Bars. Report SEMT/LISN/RT/99-003/A. 1999;CEA, France.
8. Müller G., Böhmert J. Metallographic Post-Test Investigations for the Scaled Core-Meltdown-Experiments FOREVER-1 and -2. Report FZR-298. 2000;Forschungszentrum Rossendorf, Dresden, Germany.
9. Obst, V.-D., Klenk, A., Julisch, P., Maile, K., 1988. Versuche zum Versagen einer Hauptkühlmittelleitung infolge Kriechbruch unter hohem Systemdruck (Tests about the Failure of a Main Feed Line Due to Creep under High System Pressure). Report MPA 1500 771. Stuttgart, Germany (in German).
10. Obst, V.-D., Maile, K., 1989. Versuche zur Schaffung einer Datenstruktur für die inelastische Berechnung von Kriechvorgängen in thermisch belasteten Komponenten (Tests for the Generation of a Data Base for the Non-elastic Calculation of Creep Processes in Thermally Loaded Components). Report MPA 1500 785. Stuttgart, Germany (in German).
11. Rempe, J.L., Chávez, S.A., Thinnes, G.L., Allison, C.M., Korth, G.E., Witt, R.J., Sienicki, J.J., Wang, S.K., Stickler, L.A., Heath, C.H., Snow, S.D. 1993. Light Water Reactor Lower Head Failure Analysis. Report NUREG/CR-5642. Idaho Falls.
12. Sainte Catherine C. Tensile and Creep Tests Material Characterization of Pressure Vessel Steel (16MND5) at High Temperatures (20 up to 1300 °C). Rapport SEMT/LISN/RT/98-009/A. 1998;CEA, France. (experimental data files).
13. 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. In: Proceedings of the 15th International Conference on Structural Mechanics in Reactor Technology (SMiRT-15), 15-20 August, Seoul, Korea.
14. Theofanous T.G., Liu C., Additon S., Angelini S., Kymäläinen O., Salmassi T. In-vessel coolability and retention of a core melt. Nucl. Eng. Des. 169:1997;1-48.
15. Willschütz H.-G., Altstadt E., Sehgal B.R., Weiss F.P. Coupled thermal structural analysis of LWR vessel creep failure experiments. Nucl. Eng. Des. 208:2001;265-282.
16. Willschütz, H.-G., 2002. German Patent DE 100 41 779 C 1, Steuereinrichtung für einen Kühlkreislauf (Control Device for a Cooling Circuit).
17. Willschütz H.-G., Altstadt E. Generation of a High Temperature Material Data Base and its Application to Creep Tests with French or German RPV-steel. Report, FZR-353. 2002;Forschungszentrum Rossendorf, Dresden, Germany.