Improvement of aseismic performance of a PGSFR PHTS pump |
Lee, Seong Hyeon
(Innovative System Technology Development Division, Korea Atomic Energy Research Institute)
Lee, Jae Han (Innovative System Technology Development Division, Korea Atomic Energy Research Institute) Kim, Sung Kyun (Innovative System Technology Development Division, Korea Atomic Energy Research Institute) Kim, Jong Bum (Innovative System Technology Development Division, Korea Atomic Energy Research Institute) Kim, Tae Wan (Innovative System Technology Development Division, Korea Atomic Energy Research Institute) |
1 | A.P. Villasor JR., Seismic analysis of a reactor coolant pump by the response spectrum method, Nucl. Eng. Des. 38 (1976) 527-542. DOI |
2 | K. Fujita, T. Ito, M. Tashimo, A. Sakurai, C. Kurihara, Study on the seismic response of a reactor vessel of a pool type LMFBR including fluid-structure interaction, Nucl. Eng. Des. 113 (1989) 455-462. DOI |
3 | Myung J. Jhung, Won G. Hwang, Seismic response of reactor vessel internals for Korean standard nuclear power plant, Nucl. Eng. Des. 165 (1996) 57-66. DOI |
4 | J. Buongiorno, B.D. Hawkes, Seismic analysis of heavy-liquid-metal-cooled reactor vessels, Nucl. Eng. Des. 228 (2004) 305-317. DOI |
5 | P. Chellapandi, S.C. Chetal, Baldev Raj, Effective of nuclear island connected buildings on seismic behavior of reactor internals in a pool type fast breeder reactor, Nucl. Eng. Des. 237 (2007) 2250-2264. DOI |
6 | R. Lo Frano, G. Pugliese, G. Forasassi, Preliminary seismic analysis of an innovative near term reactor: methodology and application, Nucl. Eng. Des. 240 (2010) 1671-1678. DOI |
7 | ASME Boiler and Pressure Vessel Code, Section III, Division 5, ASME, 2015. |
8 | R. Lo Frano, G. Forasassi, Preliminary evaluation of seismic isolation effects in a Generation IV reactor, Energy 36 (2011) 2278-2284. DOI |
9 | R. Lo Frano, G. Forasassi, Preliminary evaluation of the seismic response of the ELSY LFR, Nucl. Eng. Des. 242 (2012) 361-368. DOI |
10 | Jigang Meng, Shuhua Yang, Yuefang Wang, Three-Dimensional Seismic Analysis and Safety Evaluation for nuclear pump of nuclear power plant based on the RCC-M Code, Adv.Vib. Eng. 10 (No.4) (2011) 343-352. |
11 | ANSYS Mechanical APDL Manual, Theory Reference (Chapter 15.7 : Spectrum Analysis), Rev. 15.0, ANSYS Inc. |
12 | Regulatory Guide 1.92, Combining Modal Responses and Spatial Components in Seismic Response Analysis, Rev. 2, U.S. nuclear regulatory commission, 2006. |
13 | ANSYS Mechanical APDL Manual, Rev. 15.0, ANSYS Inc.. |
14 | S.H. Lee, Structural Analysis of PHTS Pump, KAERI, SFR-230-DM-306-003, 2017 rev01. |
15 | G.H. Koo, J.H. Lee, Development of FAMD code to calculate the fluid added mass and damping of arbitrary structures submerged in confined viscous fluid, KSME Int. J. 17 (No.3) (2003) 457-466. DOI |