References
- J.H. Jung, S.M. An, K.S. Ha, H.Y. Kim, Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel, Nucl. Eng. Technol. 47 (2015) 66-73. https://doi.org/10.1016/j.net.2014.11.005
- T.H. Kim, S.H. Kim, Y.S. Chang, Structural assessment of reactor pressure vessel under multi-layered corium formation conditions, Nucl. Eng. Technol. 47 (2015) 351-361. https://doi.org/10.1016/j.net.2014.12.017
- S.H. Kim, Y.S. Chang, S.C. Song, Y.J. Cho, Structural assessment of fully flooded reactor cavity and penetration piping under steam explosion conditions, Int. J. Press. Vessels Pip. 131 (2015) 36-44. https://doi.org/10.1016/j.ijpvp.2015.04.007
- L. Cizelj, B. Koncar, M. Leskovar, Vulnerability of a partially flooded PWR reactor cavity to a steam explosion, Nucl. Eng. Des. 236 (2006) 1617-1627. https://doi.org/10.1016/j.nucengdes.2006.04.018
- I.G. Cullis, J. Schofield, A. Whitby, Assessment of blast loading effects-types of explosion and loading effects, Int. J. Press. Vessels Pip. 87 (2010) 493-503. https://doi.org/10.1016/j.ijpvp.2010.07.003
- L. Cizelj, B. Koncar, M. Leskovar, Estimation of ex-vessel steam explosion pressure load, Nucl. Eng. Des. 239 (2009) 2444-2458. https://doi.org/10.1016/j.nucengdes.2009.07.023
- Sandia National Lab, IFCI 7.0 models and correlations, SAND99-1000, 1999.
- M.L. Corradini, C.C. Chu, I. Huhtiniemi, J. Murphy, S. Nilsuwankosit, J. Tang, S. Wang, User's Manual for TEXAS-V One Dimensional Transient Fluid Model, University of Wisconsin-Madison, 2002.
- OECD/NEA, OECD research programme on fuel-coolant interaction, SERENA Final Report, 2007.
- K.J. Willam, E.P. Warnke, Constitutive models for the triaxial behavior of concrete, Proc. Int. Assoc. Bridge Struct. Eng. 19 (1975) 1-30.
- A.J. Abbo, A.V. Lyamin, S.W. Sloan, J.P. Hambleton, A C2 continuous approximation to the Mohr-Coulomb yield surface, Int. J. Sol. Struct. 48 (2010) 3001-3010.
- J.L. Cela, Analysis of reinforced concrete structures subjected to dynamic loads with a viscoplastic Drucker-Prager model, Appl. Math. Model 22 (1998) 495-515. https://doi.org/10.1016/S0307-904X(98)10050-1
- N.S. Ottosen, A failure criterion for concrete, J. Eng. Mech. 103 (1977) 527-535.
- Nuclear Energy Institute, Methodology for performing aircraft impact assessments for new plant designs, NEI 07-13, 2011.
- ACI Committee 349, Code Requirements for Nuclear Safety Related Concrete Structures, American Concrete Institute, Washington, USA, 2010.
- ACI Committee 318, Building Code Requirements for Structural Concrete, American Concrete Institute, Washington, USA, 2002.
- H.T. Hu, Y.H. Lin, Ultimate analysis of PWR prestressed concrete containment subjected to internal pressure, Int. J. Press. Vessels Pip. 83 (2006) 161-167. https://doi.org/10.1016/j.ijpvp.2006.02.030
- ANSYS Civil FEM, Introduction of Civil FEM, Ver. 13.0, ANSYS Inc., 2012.
Cited by
- Structural Integrity Evaluation of a Reactor Cavity during a Steam Explosion for External Reactor Vessel Cooling vol.14, pp.12, 2016, https://doi.org/10.3390/en14123605