Papers by Keyword: BWR

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Authors: Jong Rong Wang, Hao Tzu Lin, Wan Yun Li, Shao Wen Chen, Chun Kuan Shih
Abstract: In the nuclear power plant (NPP) safety, the safety analysis of the NPP is very important work. In Fukushima NPP event, due to the earthquake and tsunami, the cooling system of the spent fuel pool failed and the safety issue of the spent fuel pool generated. In this study, the safety analysis of the Chinshan NPP spent fuel pool was performed by using TRACE and FRAPTRAN, which also assumed the cooling system of the spent fuel pool failed. There are two cases considered in this study. Case 1 is the no fire water injection in the spent fuel pool. Case 2 is the fire water injection while the water level of the spent fuel pool uncover the length of fuel rods over 1/3 full length. The analysis results of the case 1 show that the failure of cladding occurs in about 3.6 day. However, the results of case 2 indicate that the integrity of cladding is kept after the fire water injection.
Authors: Sergio Ciampolini Nogueira de Lima, Edson Pereira Soares, Marco Andreoli, Rubens Chiba, Emília Satoshi Miyamaru Seo
Abstract: When used commercially, the zirconium alloys are utilized in the shape of tubes to encapsulate the UO2 pellets in the PWR and BWR Power reactors. The metallic zirconium is an essential metallic element for the types of alloys in which the obtainment route rests in the ore opening for the production of zirconium oxide followed by the processes of pelletizing, chlorination, purification, reduction and distillation. Through the technique of X-Ray Diffraction the present phases were identified. Using the Fluorescence of an X ray it was possible to determined the chemical composition of the zirconium sponge. The mechanical properties of Vickers microhardness were obtained using a microdurometer. As a result, it was established that it is possible to define a methodology for the preparation of a sample of metallic zirconium for the microstructure analysis, as well as that its chemical purity is 97,265% linked to the microhardness of approximately 51 HV.
Authors: Yo-ichi Takeda, M. Bojinov, Hannu Hänninen, P. Kinnunen, T. Laitinen, K. Mäkelä, T. Saario, K. Sakaguchi, Tetsuo Shoji, P. Sirkiä, A. Toivonen
Abstract: A possible approach to describe the role of the environment in the phenomena behind crack initiation and crack propagation in stress corrosion cracking (SCC) is to assume that the transport of species through the oxide film on the material surface is one of the rate-controlling factors. The transport rates of ionic and electronic defects through the oxide film are, in addition to the environment, also affected by the stress and strain applied to the bulk material. In this paper, the surface oxide film formed on AISI 316L steel in slow strain rate tests (SSRT) in simulated BWR condition has been analyzed by using Electron Spectroscopy for Chemical Analysis (ESCA). The obtained film composition and structure have been combined with in-situ contact electric resistance (CER) measurements in order to evaluate the changes in oxide film electric properties during straining in the above environment. The results show that oxide film resistance of the strained part exhibits a maximum at around 2% of strain, which seems to correlate with a maximum in the Cr(III) concentration in the inner layer of the oxide. The implications of these results to SCC are discussed based on Mixed-Conduction Model (MCM).
Authors: Y. Lu, K. Sakaguchi, Tetsuo Shoji
Abstract:          
Authors: K.C. Hsieh, Kung Ting, Kuen Tsan Chen, W.F. Wu, Y.L. Lu
Abstract: The implementations of RI-ISI can improve the substantial cost reductions as well as dose reduction. From the points of the safety concern, the achievements of these procedures can identify the inspection rank to promote the integrity of the present inspection program. Thus, this paper presents the applications of RI-ISI to recirculation piping welds sensitized to IGSCC of Taiwan BWR-4 nuclear power plant. The establishment of the risk evaluation can be referenced for the regulatory and plant maintenance.
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