THERMAL HYDRAULIC ISSUES OF CONTAINMENT FILTERED VENTING SYSTEM FOR A LONG OPERATING TIME |
Na, Young Su
(Korea Atomic Energy Research Institute)
Ha, Kwang Soon (Korea Atomic Energy Research Institute) Park, Rae-Joon (Korea Atomic Energy Research Institute) Park, Jong-Hwa (Korea Atomic Energy Research Institute) Cho, Song-Won (Nuclear Safety Evaluation) |
1 | A REVA's presentation to US Nuclear Regulatory Commission, "Filtered Containment Venting Systems: General Overview and Applicability to CANDU Plants," ML12206A266 (2012). |
2 | S . W. CHO et al., "Regulatory Research of the PWR Severe Accident: Improvement of Severe Accident Analysis Method for KNSP," KINS/HR-464, Korea Institute of Nuclear Safety (2002). |
3 | Y . S. NA et al., "The Effect of the Venting Area for CFVS on the Containment," Transactions of the Korean Nuclear Society Autumn Meeting, Korea (2013). |
4 | Y . S. NA et al., "Design of Containment Filtered Venting System for Depressurization in Containment under Severe Accidents," Proceedings of ICAPP 2014, USA (2014). |
5 | R . O. Gauntt et al., "MELCOR Computer Code Manuals Vol. 1: Primer and Users Guide Version 1.8.6 September 2005," SAND 2005-5713, Sandia National Laboratories (2005). |
6 | R . O. Gauntt et al., "MELCOR Computer Code Manuals Vol. 2: Reference Manuals Version 1.8.6 September 2005," SAND 2005-5713, Sandia National Laboratories (2005). |
7 | P . C. Owczarski and K. W. Burk, "SPARC-90: A Code for Calculating Fission Product Capture in Suppression Pools," Pacific Northwest Laboratory (1991). |
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