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題 名 | 核能電廠一級設備疲勞使用因子評估=Fatigue Usage Factor of Class 1 Components for Nuclear Power Plant |
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作 者 | 陳立生; 廖炎璋; 林欣衛; 王仲賢; 林夢竹; 黃啟誠; 羅富國; 劉文仁; | 書刊名 | 台電工程月刊 |
卷 期 | 598 1998.06[民87.06] |
頁 次 | 頁8-19 |
分類號 | 449.7 |
關鍵詞 | 疲勞使用因子; 蒸汽產生器; 調壓槽; 暫態; Fatigue usage factor; Steam generator; Pressurizer; Transient; |
語 文 | 中文(Chinese) |
中文摘要 | 本文是針對核三廠蒸汽產生器(Steam Generator)與調壓槽(Pressurizer)之 40 年設計壽命的疲勞使用因子大於 0.7 以上之組件為對象, 並以應力報告書( Stress Report )之分析邏輯(符合 ASME B & PV Code Sec. Ⅲ)計算出機組運轉之疲勞使用因子 , 同時也對反應器壓力容器( Reactor Pressure Vessel )中之組件的疲勞使用因子加以 累計,再根據 FSAR 的暫態定義和前次核三計畫之經驗,並與現場運轉人員討論,將運轉中 所遭遇之暫態做明確且合理的定義,將所收集的各暫態次數,依疲勞壽命評估程序,分析出 一號機和二號機之蒸汽產生器、調壓槽與反應器壓力容器中各組件之疲勞因子歷年發展趨勢 和預估值。 |
英文摘要 | The objective of this paper is to evaluate the fatigue usage factors of the steam-generator and pressurizer at the Maanshan Nuclear Power Plant. The evaluated components included those whose end-of-life fatigue usage factors were greater than 0.7. The analysis procedure of the fatigue usage factors followed the stress reports of Westinghouse. The evaluation of fatigue usage factors of reactor-pressure-vessel components, which was developed by MRL (Material Research Laboratory) was also included in this paper. The cycle counting procedure was worked out with the existing procedure of Taiwan Power Company. The procedure can be used to count the transient cycle which were used to calculate the fatigue usage factors The fatigue life can then be evaluated and predicted. |
本系統中英文摘要資訊取自各篇刊載內容。