과제정보
This work was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) using the financial resource granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea. (No. 2103079).
참고문헌
- L.L. Humphries, T.Y. Chu, J. Bentz, R. Simpson, C. Hanks, W. Lu, B. Antoun, C. Robino, J. Puskar, P. Mongabure, OECD Lower Head Failure Project Final Report, Sandia National Laboratories, Albuquerque, NM, 2002, 87185-1139.
- R. Gauntt, D. Kalinich, J.N. Cardoni, J. Phillips, A. Goldmann, S. Pickering, M. Francis, K. Robb, L. Ott, D. Wang, C. Smith, S.S. Germain, D. Schwieder, C. Phelan, Fukushima Daiichi Accident Study (Status as of April 2012), 2012. SAND2012-6173.
- T.Y. Chu, M.M. Pilch, J.H. Bentz, J.S. Ludwigsen, W.Y. Lu, L.L. Humphries, Lower Head Failure Experiments and Analyses, vol. 5582, NUREG/CR-, 1998, pp. 98-2047.
- S. Jules, L. Flandi, K. Atkhen, Structural Assessment of a Generic PWR1000 Reactor Vessel under IVR, IVMR Project Internal Report, 2016.
- Y.J. Lee, J.M. Kim, H.M. Kim, D.H. Lee, C.K. Chung, Structural integrity evaluation of reactor pressure vessel bottom head without penetration nozzles in core melting accident, J. Comput. Struct. Eng. Inst. Korea (2014).
- 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 (3) (2015) 351-361. https://doi.org/10.1016/j.net.2014.12.017
- J.F. Mao, J.W. Zhu, S.Y. Bao, L.J. Luo, Z.L. Gao, Creep deformation and damage behavior of reactor pressure vessel under core meltdown scenario, Int. J. Pres. Ves. Pip. 139 (2016) 107-116. https://doi.org/10.1016/j.ijpvp.2016.03.009
- T.H. Lee, Y.J. Oh, I.S. Hwang, Bottom-mounted nozzle failure modes of a nuclear reactor pressure vessel under severe accident conditions, Key Eng. Mater. 297 (2005) 1652-1658. https://doi.org/10.4028/www.scientific.net/KEM.297-300.1652
- F.W. Brust, R. Iyengar, M. Benson, H. Rathbun, Severe accident condition modeling in PWR environment: creep rupture modeling, Am. Soc. Mech. Eng. Press. Vessel. Pip. Div. PVP 55638 (2013). V01AT01A054.
- J. Arndt, H. Grebner, J. Sievers, Failure assessment methodologies for pressure-retaining components under severe accident loading, Sci. Technol. Nucl. Install. (2012).
- V. Koundy, F. Fichot, H.G. Willschuetz, E. Altstadt, L. Nicolas, J.S. Lamy, L. Flandi, Progress on PWR lower head failure predictive models, Nucl. Eng. Des. 238 (9) (2008) 2420-2429. https://doi.org/10.1016/j.nucengdes.2008.03.004
- Y. Takahashi, Unified constitutive modeling of three alloys under a wide range of temperature, Int. J. Pres. Ves. Pip. 172 (2019) 166-179. https://doi.org/10.1016/j.ijpvp.2019.03.018
- Japan Nuclear Energy Safety Organization, Project of Integrity Assessment of Flawed Components with Structural Discontinuity (IAF) Material Properties Data Book at High Temperature for Dissimilar Metal Welding in Reactor Pressure Vessel, 2013 (in Japanese).
- Y. Takahashi, Development of accurate inelastic analysis models for materials constituting penetrations in reactor vessel, Denryoku Chuo Kenkyusho Hokoku 1-4 (2015).
- Y. Takahashi, Modelling of rupture ductility of metallic materials for wide ranges of temperatures and loading conditions, part I: development of basic model, Mater. A. T. High. Temp. 37 (6) (2020) 357-369. https://doi.org/10.1080/09603409.2020.1801965
- ABAQUS, Abaqus User's Manual Version 2019, Dassault Syst'emes Simulia Corp. Provid. RI, USA, 2019.
- J.L. Rempe, S. a Chavez, G.L. Thinnes, Light Water Reactor Lower Head Failure Analysis (No. NUREG/CR-5642; EGG-2618), Nuclear Regulatory Commission, Washington, DC (United States), 1993.
- B.S. Lee, J.M. Kim, J.Y. Kwon, K.J. Choi, M.C. Kim, A practical power law creep modeling of alloy 690 SG tube materials, Nucl. Eng. Technol. 53 (9) (2021) 2953-2959. https://doi.org/10.1016/j.net.2021.03.004
- Z. Gao, C. Lu, Y. He, R. Liu, H. He, W. Wang, W. Zheng, J. Yang, Influence of phase transformation on the creep deformation mechanism of SA508 Gr.3 steel for nuclear reactor pressure vessels, J. Nucl. Mater. 519 (2019) 292-301. https://doi.org/10.1016/j.jnucmat.2019.04.006
- K. Lim, Y. Cho, S. Whang, H.S. Park, Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1, Ann. Nucl. Energy 109 (2017) 337-349. https://doi.org/10.1016/j.anucene.2017.05.045