Author:
Wang Jong-Rong,Lin Hao-Tzu,Cheng Yi-Hsiang,Wang Wei-Chen,Shih Chunkuan
Subject
Nuclear Energy and Engineering
Reference11 articles.
1. Cheng, Y.H., Shih, C., Wang, J.R., Lin, H.T., 2008. Benchmark calculations of pressurizer model for maanshan nuclear power plant using TRACE code. In: Proceedings of the 16th International Conference on Nuclear Engineering (ICONE16), May 11–15, 2008, Orlando, Florida, USA, ICONE16-48603.
2. Analysis of the cooling capability of steam generators during the loss of residual heat removal system at midloop operation with closed primary system;Gonza’ lez;Annals of Nuclear Energy,2006
3. Phenomenology during the loss of residual heat removal system at midloop conditions with pressurizer PORVs open: associated boron dilution;Gonza’ lez;Annals of Nuclear Energy,2007
4. Jaeger, W., Lischke, W., Espinoza, V.H.S., 2007. Safety related investigations of the VVER-1000 reactor type by the coupled code system TRACE/PARCS. In: Proceedings of ICONE15: 15th International Conference on Nuclear Engineering, April 22–26, 2007, Nagoya, Japan, ICONE15-10438.
5. Jasiulevicius, A., Zerkak, O., Macian-Juan, R., 2007. Simulation of OECD/NEA ROSA test 6.2 using TRACE. In: Proceedings of ICONE15: 15th International Conference on Nuclear Engineering April 22–26, 2007, Nagoya, Japan, ICONE15-10192.
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