碩士 / 國立清華大學 / 核子工程與科學研究所 / 102 / In the present study, a MELCOR input deck for the Chinshan Nuclear Power Station of Taiwan Power Company is developed. Chinshan nuclear power station employs a Boiling Water Reactor (BWR IV) designed by General Electric and Mark I containment. The input deck is used to analyze the station blackout sequence, and the results will be compared with the MAAP5.
The work involved in the study includes: (1) Use the MELCOR input deck from INER as the basis. Build a new MELCOR input deck of Chinshan nuclear power station according to the MAAP5 input deck and the corresponding calculation sheets from INER. (2) Initialize the new MELCOR input deck to staeday state. (3) Simulate the SBO event of the plant using MELCOR and MAAP5 codes with the assumption that the core melt occurs under high pressure and low pressure. (4) Compare the results of these two codes. The major focus are the timing of major events, the thermal hydraulic responses of reactor coolant system and containment, hydrogen generation, the radionuclide releases from core during the core melt and during the molten core concrete interactions, and the fraction of radionuclide releasing to the environment.
Compared the results, it has been found that: (1) MELCOR has a more detailed modeling of core and vessel internal regions. It consists of 3 radial rings and 13 axial levels. MAAP5 treats the core as a single volume. (2) The reactor vessel bottom attack model amd mode of its failure of these two codes are also significantly different. (3) The amount of hydrogen generation during the core melt as predicted by these two codes are significantly different. The impacts of flow blockage on the prediction of hydrogen generation of these two codes are different. MAAP5 is more sensitive to the assumpation of flow blockage. (4) The classification of radionuclide groups is different. Due to the difference in the modeling of core region, the predicted in-vessel releases of radionuclide is different. The predicted ex-vessel releases are also significantly different due to difference in the modeling of core concrete interactions. The fraction of each radionuclide released to the environment is different. (5) The MELCOR results are very sensitive to the time step size. If the time step size has not been set properly, the code stops calculation prematurely.
| Identifer | oai:union.ndltd.org:TW/102NTHU5265014 |
| Date | January 2014 |
| Creators | Cheng, Hsin, 鄭欣 |
| Contributors | 李敏 |
| Source Sets | National Digital Library of Theses and Dissertations in Taiwan |
| Language | zh-TW |
| Detected Language | English |
| Type | 學位論文 ; thesis |
| Format | 86 |
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