Facility Details: FOREVER

References: [1] Sehgal, B. R., Giri, A., Chikkanagoudar, U., Karbojian, Aram, Experiments on in-vessel melt coolability in the EC-FOREVER Program. Nucl. Eng. Des. 236(19-21), 2199-2210, ISSN: 0029-5493.

[2] Sehgal, B. R., Karbojian, Aram, Giri, Asis, Kymalainen, O., Bonnet. M. J., Ikkonen, K., Sairanen, R., Bhandari, S., Buerger, M., Dienstbier, J., Techy, Z., Theofanous, T., Assessment of reactor vessel integrity (ARVI). Nucl. Eng. Des. 235(04), 213-232, ISSN: 0029-5493, February.

3] Sehgal, B. R., Giri, Asis, Chikhanagoudar, Utkarsh, Karbojian, Aram, 2004. Experiments on in-vessel melt coolability in the EC-FOREVER program, Proceedings of, International Congress on Advances in Nuclear Power Plants, ICAPP'04, Pittsburgh, PA, USA, 917-927, 13 June - 17 June.

[4] 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, Proc. 15th Int. Conf. on Structural Mechanics in Reactor Technology (SMiRT- 15), Seoul, Korea, 15-20 August.

[5] Sehgal B.R., Nourgaliev, R.R., Dinh, T.N., A.K. Karbojian, 1998. Integral experiments on in-vessel coolability and vessel creep: results and analysis of the FOREVER-C1 Test. Proc. Workshop on Severe Accident Research in Japan, SARJ-98, Japan, November.

[6] 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. Part I: Experiments and experimental data. 15th International Conference on Structural Mechanics in Reactor Technology (SMiRT-15), Seoul, Korea, 15-20 August.

[7] Sehgal, B.R., Nourgaliev, R.R., Dinh, T.N., Karbojian, A., Bui, V.A., Green, J.A., 1998. Forever experiments on thermal and mechanical behavior of a reactor pressure vessel severe accident, OECD/CSNI Workshop on “In-Vessel Core Debris Retention and Coolability”, Garching, Germany, 3-6 March.

[8] Theerthan, S.A., Karbojian, A. and Sehgal, B.R., 2001, FOREVER experiments on thermal and mechanical behavior of reactor pressure vessel during a severe accident: EC FOREVER-1 test. SMiRT-16, Washington DC, USA, 12-17August.

[9] Willschuetz, H.-G., Altstadt, E., Moessner, T., Weiss, F.-P., Sehgal, B. R., 2000. A finite element model for pre- and post-test calculations of the FOREVER experiments, Proc. ICONE8, 8th Int. Conf. on Nuclear Engineering, Baltimore, MD, USA, 2-6 April.

[10] Willschuetz, H.-G., Altstadt, E., Weiss, F.-P., Sehgal, B. R., 2000. A finite element pre- and post-test calculations of the FOREVER experiments, Annual Meeting on Nuclear Technology, Kerntechnische Gesellschaft e.V., 23-25 May.

[11] B.R. Sehgal, T.N. Dinh, R.R. Nourgaliev, V.A. Bui, J. Green, G. Kolb, A. Karbojian, S.A. Theerthan, A. Gubaidulline, M. Helle, O. Kymäläinen and H. Tuomisto, B.D. Turland, G.P. Dobson, K. Ikonen, N. Kolev, J.M. Bonnet, S. Rougé, M. Narcoux, A. Liégeois, A. Siccama, F. Parozzi, M. Caira. Final report for the ""Melt-Vessel Interactions"" Project. MVI Project Final Research Report, 479 p. April 15, 1999 [https://www.stralsakerhetsmyndigheten.se/contentassets/826ae715ef574a0081bab9f9d1912910/0053-final-report-for-the-melt-vessel-interactions-mvi-project].
IP/Copyright Situation: Data available in the published papers only

References: [1] W. Ma, A. Karbojian, N. Dinh. Data Compilation for FOREVER and SIMECO Tests. Technical Report for SARNET Network of Excellence for a Sustainable Integration of European Research on Severe Accident.

[2] P. Yu, W. Ma, W. Villanueva, A. Karbojian, S. Bechta. Validation of a thermo-fluid-structure coupling approach for RPV creep
failure analysis against FOREVER-EC2 experiment. Annals of Nuclear Energy 133 (2019) 637–648.
IP/Copyright Situation: To be Checked