查詢結果分析
來源資料
相關文獻
- 核三廠爐水銹垢取樣技術與特性鑑定探討
- 核三廠水化學運轉模式與爐水銹垢特性探討
- IIST設施自發式爐心冷卻系統設計及事故分析研究
- Taipower's Transient Analysis Methodology for Pressurized Water Reactors
- 壓水式反應器射棒分析方法
- RELAP5/MOD3.2程式分析IIST模擬小破口冷卻水流失爐心冷卻不足實驗之研究
- Neutronics Feasibility Studies of a Pwr Core with Mixed Oxide Fuels in the Republic of China
- 獨立「壓水式反應器主蒸汽管斷裂分析方法」之建立與應用
- RETRAN-02/FREY壓水式反應器RCP轉子卡死分析方法
- 壓水式反應器燃料佈局之最佳化研究
頁籤選單縮合
題名 | 核三廠爐水銹垢取樣技術與特性鑑定探討=Sampling Technique and Property Characterization of Circulating Cruds in Reactor Coolant System of Maanshan Nuclear Power Plant |
---|---|
作者 | 溫冬珍; 陳蜀瓊; 陳孟仁; 陳仁德; 江明昆; 許天佑; 黃佳伸; | 書刊名 | 台電工程月刊 |
卷期 | 595 1998.03[民87.03] |
頁次 | 頁24-36 |
分類號 | 449.2 |
關鍵詞 | 壓水式反應器; 銹垢; 一次冷卻系統; 鋰/硼化學; Pressurized water reactor; PWR; Crud; Primary cooling system; Lithium/Boron chemistry; |
語文 | 中文(Chinese) |
中文摘要 | 本報告係“核三廠反應爐水及相關系統�蚴神牯A研究”委託計畫之一部份,主要 針對壓水式反應器一次系統冷卻水生成之腐蝕產物,在運轉中常導致廠區輻射場增建及系統 熱傳特性改變,探討其�蚴租捰阱H運轉條件及結構材質而變化之情形與影響。利用所建立之 高壓冷卻水系統�蚴祠�樣設備與技術,在功率運轉及停機期間,藉由不同孔隙度之聚碳酸鹽 微細濾膜過濾水樣,獲取適量粒子�蚴砥A再以掃瞄電子顯微鏡及X-射線繞射能譜分析法鑑 定其結構與元素;而以化學溶解�蚴神嶀尷R不同粒徑�蚴砟尿@度及其核種活度。一次系統冷 卻水參數pH□,於兩個機組第l0燃料週期運轉時,則由硼、鋰濃度計算而得,結果顯示燃 料末期遞載運轉時之pH□變化較大。 |
英文摘要 | This report is a pant of the project "Study on the crud morphology of reactor water and related system for MNPP "sponsored by the Taiwan Power Company. Due to the corrosion products formed in pressurized water reactor(PWR) coolant system cause lots of problems problems for plant operating such as resulting in radiation field build-up and change of heat transfer characteristics. The aim of this study is to investigate the composition of suspended particles in primary side varies with reactor operating conditions and structural materials. During the power operation and shutdown period, a considerable amount of crud samples could be obtained with the well-established sampling technique and equipment that provided for high pressure coolant filtration with various pore size polycarbonate membranes. The cruds were characterized by a combination of scanning electron microscope (SEM) and energy dispersion analysis by X-rays (EDAX). While the concentration of major components and its specific activity of the crud for different size ranges were analyzed by ICP and MCA with chemical method using the dissolution technique. The parameter of high temperature primary coolant pH□ values in fuel cycle 10 for both units of Maanshan Nuclear Power Plant (MNPP) were calculated from boron and lithium concentration. The result revealed that the pH□ control regimes at the end of cycle was affected significantly by the power coastdown. |
本系統之摘要資訊系依該期刊論文摘要之資訊為主。