Integral effect test for steam line break with coupling reactor coolant system and containment using ATLAS-CUBE facility |
Bae, Byoung-Uhn
(Innovative System Safety Research Division, Korea Atomic Energy Research Institute)
Lee, Jae Bong (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) Park, Yu-Sun (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) Kim, Jongrok (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) Kang, Kyoung-Ho (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) |
1 | Masahiro Ishigaki, Satoshi Abe, Yasuteru Sibamoto, Taisuke Yonomoto, Experiment on density stratification behavior by containment venting using CIGMA facility, in: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), Portland, US, August 18-22, 2019. |
2 | Jeongyun Kim, Young-Seok Bang, Development of RCS-containment coupled analysis model and evaluation of LBLOCA for APR-1400, in: Proceedings of the International Conference Nuclear Energy for New Europe, Bled, Slovenia, 2017, pp. 11-14. September. |
3 | Soon Joon Hong et al., "Development of CAP code for nuclear power plant containment: Lumped model", Nuclear Engineering and Design, vol. 291, pp. 47-63, 2015. DOI |
4 | J.B. Lee, et al., "Description Report of ATLAS Facility and Instrumentation (Third Revision)," KAERI/TR-8106/2020, Korea Atomic Energy Research Institute, 2020. |
5 | Yeon-Sik Kim, et al., Analysis of a station blackout scenario with an ATLAS test, Nucl. Eng. Technol. 45 (2) (2013) 179-190. DOI |
6 | A. Dehbi, A generalized correlation for steam condensation rates in the presence of air under turbulent free convection, Int. J. Heat Mass Tran. 86 (2015) 1-15. DOI |
7 | American Nuclear Society, Draft ANS-5.1/N18.5, Decay Energy Release Rates Following Shutdown of Uranium Fueled Thermal Reactors, October 1973. |
8 | D. Paladino, O. Auban, M. Huggenberger, M. Andreani, Investigation of light gas effects on passive containment cooling system in ALWR, in: Proceedings of 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-10), 2003. |
9 | H. Uchida, et al., Evaluation of post-incident cooling systems of light-water power reactors, in: Proceedings of International Conference on Peaceful Uses of Atomic Energy, vol. 13, 1965, pp. 93-102. |
10 | K.Y. Choi, et al., Scaling Analysis Report of the ATLAS Facility," KAERI/TR-5465/2014, Korea Atomic Energy Research Institute, 2014. |
11 | OECD/NEA, Agreement on the OECD/NEA HYMERES Project; to Resolve Complex Safety Relevant Issues for the Analysis and Mitigation of a Severe Accident Leading to Hydrogen Release into a Nuclear Plant Containment, 2012. |
12 | Y.S. Na, et al., Current State of the Construction of an Integrated Test Facility for Hydrogen Risk", 2016, Autumn Meeting of the KNS, Kyungju, Korea, 2016. Oct 26-28. |
13 | C. Ghitiu, et al., Containment spray experiments in MISTRA facility for heat and mass transfer model validation in superheated atmosphere, in: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH18), Portland, US, August 18-22, 2019. |
14 | M. Ishii, et al., The three-level scaling approach with application to the purdue university multi-dimensional integral test assembly (PUMA), Nucl. Eng. Des. 186 (1998) 177-211. DOI |
15 | M.S. Ko, et al., "RCS Coupled Containment Simulator Experiment Design Assessment", KAERI/CM-2771/2018, Korea Atomic Energy Research Institute, 2018. |
16 | B.U. Bae, et al., Integral Effect Test of Steam Line Break Accident Using ATLASCUBE (Containment Utility for Best-Estimate Evaluation) Facility, " Korea Nuclear Society Autumn Meeting, Goyang, Korea, 2019. October 24-25. |
17 | R.C. Schmitt, et al., Simulated Design Basis Accident Tests of the Carolinas Virginia Tube Reactor Containment - Final Report, IN-1403, Idaho Nuclear Corporation, 1970. |
18 | OECD/NEA report, OECD/NEA THAI Project: Hydrogen and Fission Product Issues Relevant for Containment Safety Assessment under Severe Accident Conditions, NEA/CSNI/R(2010) 3, 2010. |
19 | OECD/NEA, International Standard Problem ISP-47 on Containment Thermal Hydraulics, vol. 10, NEA/CSNI/R, 2007, p. 2007. |