現今核能反應器內部大小組件大多使用304和316不鏽鋼為材料，而這些材料常見的腐蝕現象主要是沿晶應力腐蝕龜裂(Intergranular Stress Corrosion Cracking, IGSCC)與輻射促進應力腐蝕龜裂(Irradiation-Assisted Stress Corrosion Cracking, IASCC)，已被證實和沸水式反應器(Boiling Water Reactor, BWR)內部管件系統和壓力槽內部主件損壞有關，對電廠運轉安全造成嚴重威脅，而決定損壞發展情況最重要的參數是電化學腐蝕電位(Electrochemical Corrosion Potential, ECP)。近年來，全世界核能電廠逐漸廣泛利用加氫水化學(Hydrogen Water Chemistry, HWC)技術，透過飼水注氫以降低水中溶氧濃度，進而使沸水式反應器電廠主冷卻水迴路中各組件的電化學腐蝕電位降低至-0.23VSHE以下，期望達到抑制腐蝕保護主件之目的。
不論是何種世代的反應器，確保運轉的安全是首要任務，其中，使主冷卻水迴路中的冷卻水化學環境達到最佳化是非常重要的。然而，因為反應器壓力槽內部的高輻射劑量和結構設計造成實際量測所有區域的腐蝕電位十分困難而不可行，故採取電腦程式模擬計算腐蝕電位ECP被認為是相對理想可行的辦法。

進步型沸水式反應器(Advanced Boiling Water Reactor, ABWR)是屬於第三代(Generation III)型式的核反應器，為傳統BWR改良簡化而來，主要不同之處在於以爐內泵(Reactor Internal Pump, RIP)取代舊有BWR的再循環水泵，此改變是否影響HWC對於ABWR的有效性或是和對BWR的影響有無不同之處是值得探討關心的議題。本研究針對第三代進步型反應器，以ABWR（位於台灣北部之核四龍門電廠）為模擬對象，利用由原始DEMACE電腦程式修正而來的DEMACE_ABWR程式，配合電廠本身各組件物理尺寸資料、主冷卻水之輻射分解、熱流分析結果和中子物理計算輻射劑量等輸入結果，模擬計算並分析其在一般水化學(Normal Water Chemistry, NWC)和加氫水化學的飼水注氫量涵蓋0.1~2ppm範圍之下，主冷卻水迴路中的水化學概況和重要組件材料所處環境的電化學腐蝕電位。
數值模擬分析結果顯示，在NWC下ABWR和傳統BWR一樣都有因為水的輻射分解造成冷卻水含氧量過高的問題，尤其是中子及加馬射線劑量率極高的爐心燃料匣區，其ECP值大約為0.25V；但在實施HWC飼水注氫量約0.4 ppm後，主冷卻水迴路( Primary Coolant Circuit, PCC )幾個重要位置的冷卻水溶氧濃度都明顯下降，尤其是RPV Bottom Drain 效益最好，此外，RIP亦受到HWC的保護作用，ECP都在-0.23V以下，由此可見HWC確實對PCC中的各個組件發揮了抑制腐蝕的功效，可確保未來核四龍門電廠的運轉安全。

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[64] 林金足，龍門電廠RETRAN系統最佳估算模式建立計算書，行政院原子能委員會核能研究所，台灣，中華民國一百年三月。