研究生: |
蕭德勇 Hsiao, Te-Yung |
---|---|
論文名稱: |
壓水式反應器暫態辨識之研究 The Transient Identification for Pressurized Water Reactor |
指導教授: |
林強
Lin, Chaung |
口試委員: |
施純寬
白寶實 苑穎睿 張欽章 林強 |
學位類別: |
博士 Doctor |
系所名稱: |
原子科學院 - 工程與系統科學系 Department of Engineering and System Science |
論文出版年: | 2012 |
畢業學年度: | 100 |
語文別: | 中文 |
論文頁數: | 74 |
中文關鍵詞: | 壓水式反應器 、暫態辨識 |
外文關鍵詞: | Pressurized Water Reactor, Transient Identification |
相關次數: | 點閱:1 下載:0 |
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一旦壓水式反應器發生暫態事件,如果運轉員可以辨識其類型,將有助於使系統回到安全運轉狀態。監測反應器之熱狀態,反應器冷卻系統(Reactor Cooling System,RCS)之溫度與壓力,可以幫助運轉員掌握飽和餘裕及事件的發展。在本研究中,先後發展了決定性與隨機性方法做為異常事件辨識之用。決定性方法除上述溫度與壓力外,另以反應器冷卻系統冷端與熱端溫差做為第3個系統關鍵參數;隨機性方法則增加蒸汽產生器壓力為第4個系統關鍵參數。
事件數據使用RELAP5最佳估算模式進行模擬,由其中可觀察到每個事件之暫態反應系統關鍵參數都有其特性,決定性方法利用在特有之辨識時間內之變動範圍及熱狀態變化趨勢做為事件辨識。隨機性方法以每個事件其數據的機率累加分配,每0.05為增量,從0.05到1.00,做為事件之基本資料,用作辨識區分之用。考慮量測存在雜訊,模擬的數據以亂數方式加以處理,而得到95%的信賴區間,做為異常事件資料庫之數據。辨識一個事件必須符合80個數值之比較,這些數據分別屬於4個系統關鍵參數。
由於辨識過程簡單,在非常短的時間即可完成。驗證結果皆能有效地辨識暫態事件,此兩種方法將有助於運轉員更有效地執行緊急操作程序。
Once an event in a pressurized water reactor (PWR) occurs and the operator has identified it, the system may then be returned to safe operational status. Usually, monitoring the thermal state of the reactor, e.g., the temperature and pressure of the reactor cooling system (RCS), the operator can realize the margin to the safety limit and the progress of the event. A deterministic approach and a stochastic approach are developed in this study. In deterministic approach, the temperature difference between hot and cold legs is additionally adopted as the third parameters used for identification. And, the steam generator pressure is adopted as the forth parameter in stochastic approach.
The event data are generated using the best estimated model RELAP5. In deterministic approach, since the variation ranges of system key parameters at a specific time duration represent the specific character of each initiating event, the identification procedure can easily determine the case by comparing the variation range of on-line data and the event data in data pool. In the stochastic approach, which accounts for measurement noise, the cumulative distribution function (CDF) is constructed and system parameters variables at the cumulative probability from 0.05 to 1.00, with 0.05 increments, are chosen for identification. The random value is added to the simulated data, and then a 95% confidence interval is obtained. To identify an event, eighty data points, i.e., twenty data points for each parameter and four parameters for each event, should match the stored data.
Since the identification procedures are simple, the computation is very fast and the results show that the event can be properly identified. These two methods will be beneficial in the context of executing an emergency operating procedure more effectively.
1. Embrechts, M.J., Benedek, S., “Hybrid identification of nuclear power plant transients with artificial neural networks”, IEEE Trans. on Industry Electron. 51,2004,686 – 693.
2. Lee, S.J., Seong, P.H., “A dynamic neural network based accident diagnosis advisory system for nuclear power plants”, Annals of Nuclear Energy 46, 2007, 268-281.
3. Santosh, T.V., Vinod, G., Saraf, R.K., Ghosh, A.K., Kushwaha,H.S., “Application of artificial neural networks to nuclear power plant transient diagnosis”, Reliability Engineering & System Safety 92, 2007, 1468-1472.
4. Marseguerra, M., Zoia, A., “The auto associative neural network in signal analysis: II. Application to on-line monitoring of a simulated BWR component”, Annals of Nuclear Energy 32, 2005, 1207-1223.
5. Roverso, D., “Soft computing tools for transient classification”, Information Science: an International Journal 127, 2000, 137 – 156.
6. Roverso, D., “Plant diagnostics by transient classification: The ALADDIN approach”, International Journal of Intellegence System 17, 2002, 767 – 790.
7. Roverso, D., “Fault diagnosis with the ALADDIN transient classifier, system diagnosis and prognosis: security and condition monitoring issues", Conference No 3, Orlando FL, ETATS-UNIS (21/04/2003) 5107, 2003,162-172.
8. Roverso, D., “Dynamic empirical modeling techniques for equipment and process diagnostics in nuclear power plants”, International Journal of Nuclear Knowledge Management. 2, 2005, 239 – 248.’
9. Kwon, K.C., “HMM-based transient identification in dynamic process”, Transaction on Control Automation, and System Engineering 2, 2000, 40-4.
10. Cholewa,W.,Frid, W., Bednarski,M., “Identification of loss-of-coolant accidents in LWRs by inverse models”, Nuclear Technology 147, 2004, 216-226.
11. Marseguerra, M., Zio, E., Oldrini, A., Brega, E., “Fuzzy identification of transients in nuclear power plants”, Annals of Nuclear Engineering and Design 225, 2003, 285-294.
12. Zio E., Baraldi P. and Roverso D., “An extended classifiability index for feature selection in nuclear transients”, Annals of Nuclear Energy 32, 2005, 1632-1649.
13. MOL Antionio, C.A., ALMEIDA José, C.S., PEREIRA Claudio, M.N.A., MARINS Eugenio, R., LAPA Celso Marcelo, F., “Neural and genetic-based approaches to nuclear transient identification including ‘don’t know’ response”, Progress in Nuclear Energy 48, 2005, 268-282.
14. Mo, K., Lee, S.J., Seong, P.H., “A dynamic neural network aggregation model for transient diagnosis in nuclear power plants”, Progress in Nuclear Energy 49, 2007. 3262-272.
15. Gottlieb, C., Anov, V., Gudowski, W., Garis, N., “Feasibility study on transient identification in nuclear power plants using support vector machines”, Nuclear Technology 155, 2005, 67-77.
16. Antonio, J., Medeiros, C.C., Schirru, R., “Identification of nuclear power plant transients using the particle swarm optimization algorithm”, Annals of Nuclear Energy 35, 2007, 576-582.
17. Baraldi, P., Pedroni, N., Zio, E., “Application of a niched pareto genetic algorithm for selecting features for nuclear transients classification”, International Journal of Intelligence System 24, 2009.118-151.
18. Nicolau, A.S., Schirru, R., Meneses, A..A..M., “Quantum evolutionary algorithm applied to transient identification of a nuclear power plant”, Progress in Nuclear Energy 53, 2011, 86e91.
19. Hadad, K., Pourahmadi, M., Majidi-Maraghi, H., “Fault diagnosis and classification based on wavelet transform and neural network”, Progress in Nuclear Energy 53 (2011), 2011, 41e47.
20. Lin, C, Chang, H.J., “Identification of pressurized water reactor transient using template matching”, Annals of Nuclear Energy 38, 2011, 1662–166.
21. Yuann, R.Y., Hsiue, J.K., Chen, P.C., Chang, J.S., “Transient and accident fast diagnostic system”, Third International Topical Meeting On Nuclear Power Plant, Seoul, Korea, 1988, B5-32–B5-40.
22. Moody, F.J., “Introduction to Unsteady Thermofluid Mechanics”, Wiley, New York, 1990.
23. 陳順宇、鄭碧娥,「統計學」,華泰出版社,2004年。