The integrity of the RV support system of the Korean Standard Nuclear Plant Plus (KSNP+) is investigated for a postulated RV closure head drop accident. This was considered due to the adoption of the IHA (Integrated Head Assembly) in KSNP+ reactor design, which causes the increase of the weight of the RV closure head assembly. The head drop accident could be anticipated during the RV head handling process. The drop event may cause an impact load on the RV and support system. Three different scenarios and three different analysis models were considered and developed for the head drop analysis. The entire reactor vessel and support system are modeled by using lumped masses and beam elements. The nonlinear elasto-plastic dynamic analyses were performed using a commercial code to evaluate the time-dependent behavior of the support columns. The analysis results show that the local plastic deformation occurs in the columns, but the plastic deformation in overall cross section does not occur. As a result, the RV support system would remain intact, and continue to support the reactor vessel in such an accident.
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ASME 2005 Pressure Vessels and Piping Conference
July 17–21, 2005
Denver, Colorado, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4188-X
PROCEEDINGS PAPER
An Evaluation of the Integrity of the Reactor Vessel Support System for a Postulated Reactor Vessel Closure Head Drop Accident of KSNP+
Young Jin Byun,
Young Jin Byun
Korea Power Engineering Company, Daejeon, Korea
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Ki Kwang Sung,
Ki Kwang Sung
Korea Power Engineering Company, Daejeon, Korea
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Dae Hee Lee,
Dae Hee Lee
Korea Power Engineering Company, Daejeon, Korea
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Taek Sang Choi
Taek Sang Choi
Korea Power Engineering Company, Daejeon, Korea
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Young Jin Byun
Korea Power Engineering Company, Daejeon, Korea
Ki Kwang Sung
Korea Power Engineering Company, Daejeon, Korea
Dae Hee Lee
Korea Power Engineering Company, Daejeon, Korea
Taek Sang Choi
Korea Power Engineering Company, Daejeon, Korea
Paper No:
PVP2005-71681, pp. 477-483; 7 pages
Published Online:
July 29, 2008
Citation
Byun, YJ, Sung, KK, Lee, DH, & Choi, TS. "An Evaluation of the Integrity of the Reactor Vessel Support System for a Postulated Reactor Vessel Closure Head Drop Accident of KSNP+." Proceedings of the ASME 2005 Pressure Vessels and Piping Conference. Volume 3: Design and Analysis. Denver, Colorado, USA. July 17–21, 2005. pp. 477-483. ASME. https://doi.org/10.1115/PVP2005-71681
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