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題 名 | 核一廠放射性廢料固化系統改善研究=Improvement of the Solidification System in First Nuclear Power Plant |
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作 者 | 黃慶村; 陳乂平; 田景光; 劉增明; 黃萬芬; | 書刊名 | 台電工程月刊 |
卷 期 | 695 民95.07 |
頁 次 | 頁18-29 |
分類號 | 449.8 |
關鍵詞 | 高效率固化; 脫水; 硫酸鈉; High-efficiency solidification; Dehydration; Sodium sulfate; |
語 文 | 中文(Chinese) |
中文摘要 | 本研究是以核一廠固化廠房現有之空間,規劃興建高效率固化系統之可行性評估,與提供改善方案以解決原有固化系統中廢棄物桶輸送設備與離心脫水設備產生之問題。 在高效率固化系統興建之空間規劃與評估方面,根據高效率固化技術之流程,及核一廠濕性廢棄物之處理需求容量與預定安裝地點之空間條件,研擬完成包含與不包含廢液蒸發單元等兩種系統設計方案,並進行兩種設計方案之利弊分析,以供決策之參考。這兩種設計基本上皆可進行包括粉狀廢樹脂、濃縮廢漿與污泥等之固化,惟不包含廢液蒸發單元之設計在操作上會有較多之限制。研究顯示核一廠現有的空間可以滿足高效率固化系統建立的需求。 有關廢棄物桶輸送設備改善以及固化系統離心脫水設備粉塵洩漏放射性污染擴散問題之改善等問題,在本研究中已併入高效率固化系統興建中整體解決。其中輸送設備擬改建為滾輪輸送機,可避免原有懸臂式輸送機,在廢棄物桶輸送操作上易發生之定位與洩料困難等問題;離心脫水設備則規劃改用姜生式過濾篩(Johnson screen)之真空過濾器,該式過濾篩能免除阻塞現象,易於反洗,而以真空方式進行脫水,則可避免發生粉塵外逸,徹底免除放射性污染問題。 此外,對固化系統濃縮廢漿槽因硫酸鈉發生結晶現象而無法泵送之問題,也以添加氫氧化鋇溶液方式進行實驗,證實可將硫酸鈉結晶轉化為含硫酸鋇與氫氧化鈉之漿液,不僅可進行泵送,形成之漿體也可直接以高效率固化系統進行固化。 本研究成果對核一廠濕性廢棄物減容與安定化處理技術與設備之精進,具有實質的助益。 |
英文摘要 | This research is to design and evaluate a plan of building high-efficiency solidification system in the avaliable space of original solidification facility and provide a way to improve orginal transportation system and centrifugal equipment. According to the capacity that first Nuclear Power Plant demand and geometric dimensions of the available space for the system to be build in, INER developed two options in which evaporation unit is an alternative. Both designs are able to conduct the process of solidification for power spent resins, concentrated waste and sludge. However, the one without evaporation unit would have more limitations when operating authentically. The system layout provided in this study demonstrates the high-efficiency solidification system can be well fitted in the available space. The improvement of both original transportation system and centrifugal equipment is integrated in high-efficiency solidification system. Replacing original transportation equipment of suspended type with a roller type can avert drawbacks that is not easy to pinpoint position and discharge waste. The existing centrifugal dehydration equipment is planned to be substituted for a vacuum filter equipped with Johnson Screen, which is able to ward off blocking and easily maintained by backwashing. Thus, it will thoroughly settle the problem of leakage and radioactive particles spread happening in the original centrifugal dehydration equipment. Moreover, this project proves an effective method in the laboratory to transform sodium sulfate crystal into mixtures of barium sulfate and sodium hydroxide by reacting with barium hydroxide. It helps not only pump the liquid waste out of the storage tank smoothly but the reaction product can also be used in the high-efficiency solidification process directly without further treatment. The research results indicate that it provides concrete benefits for the improvement on both technology and equipment of volume reduction and stabilization of the wet radioactive waste in First Nuclear Power Plant. |
本系統中英文摘要資訊取自各篇刊載內容。