裂縫成長速率(Crack Growth Rate，簡稱CGR)的量測是了解各種使用於核電廠輕水式反應器(Light Water Reactor，簡稱LWR)環境中材料之環境促進破裂(Environmentally Assisted Cracking，簡稱EAC)的一種重要工具。此外，這種量測也被用來產生腐蝕疲勞(Corrosion Fatigue，簡稱CF)與應力腐蝕破裂(Stress Corrosion Cracking，簡稱SCC)的量化數據。而這些數據基本上不但可用來進行結構的完整性分析，也可針對已存在或假設會產生的缺陷進行材料使用壽命(lifetime)的可靠度評估。
本論文主要是論述兩種分別擁有低硫含量(A508 Cl.2, 0.008 wt.%)或高硫含量(A533B Cl.1, 0.018 wt.%)之核子級反應器壓力槽(Reactor Pressure Vessel，簡稱RPV)低合金鋼(Low-Alloy Steel，簡稱LAS)，在模擬沸水式反應器(Boiling Water Reactor，簡稱BWR) 288oC高溫水環境下的CF與SCC行為。實驗結果顯示：RPV LAS之CGR受到各種機械因素如應力強度因子範圍(stress intensity factor range，簡稱∆K)、負荷頻率(loading frequency，簡稱ν)、上升時間(rise time，簡稱ΔtR)，以及在最大負荷處的維持時間(hold time，簡稱ΔtH)等的影響。在CF的試驗中，結果發現在相同的水質與負荷條件下，CGR會隨著∆K的上升而增加。此外，若在∆K值相似的情形下，ν越高(或ΔtR越短)，則CGR會越快。而在SCC的試驗中，則可觀察到若使用週期性部分卸除負荷(Periodic Partial Unloading，簡稱PPU)的情形之下，ΔtH越長，則CGR會越慢。
另一方面，本研究亦發現不論在CF或SCC的試驗中，高溫水中的溶氫(Dissolved Hydrogen，簡稱DH)會降低材料的電化學電位(Electro-Chemical Potential，簡稱ECP)，進而能夠有效降低CGR。DH對CGR抑制效應的機制與裂縫尖端(crack tip)附近的水化學狀況也將在本論文中作探討。又，在BWR之正常水化學(Normal Water Chemistry，簡稱NWC)環境中，鋼材中的含硫量於低頻負荷(例如ν < 4×10-3 Hz)、低流速的氧化(例如ECP = 100-200mVSHE)條件下對裂縫成長速率的影響並不十分明顯。
當各種測試試片藉由特殊的電化學方法(ENDOX treatment)移除氧化物以估算其平均的裂縫長度之後，實驗結果發現：除了少數處於加氫水化學(Hydrogen Water Chemistry，簡稱HWC)的數據以外，多數的CGR數據均可與一些適用於BWR環境下的預測模型相比較。然而，目前實驗所得到在低頻負荷(ν = 4×10-4 Hz)下之CF CGR的數據，並不能被Eason所發展的預測模型所規範。此外，大多數的SCC CGR之數據，並不能被MPA Stuttgart模型所涵蓋。

Crack growth rate (CGR) measurement is an important tool to understand the behaviors of the environmentally assisted cracking (EAC) of various materials used in light water reactor (LWR) environments. In addition, such measurements are also used to produce quantitative data on corrosion fatigue (CF) and stress corrosion cracking (SCC). This type of data is essential for structural integrity analyses, as well as for the lifetime estimation and reliability of existing or postulated defects.
In this paper, behaviors of CF and SCC experiments with two different nuclear grade reactor pressure vessel (RPV) low-alloy steels (LAS) with low- (A508 Cl.2, 0.008 wt.%) or high-sulfur (A533B Cl.1, 0.018 wt.%) steel content at 288°C under simulated boiling water reactor (BWR) conditions are presented. CGR of RPV LAS was found to be dependent upon various mechanical factors such as the stress intensity factor range (∆K), loading frequency (ν), rise time (ΔtR), and hold time (ΔtH) at maximum load. In CF tests, it was observed that the CGR increased as ∆K increased under the same water quality and loading conditions. If ∆K was similar, the higher the ν (or the shorter ΔtR), the higher was the CGR. In SCC tests, the longer the ΔtH, the slower the CGR was under periodic partial unloading (PPU) conditions.
On the other hand, it was found that dissolved hydrogen (DH), which lowered the electrochemical potential (ECP), could effectively suppress the CGR in either CF or SCC tests. The mechanism of the suppressive effect of DH on the CGR and the water chemistry conditions near the crack tip was also discussed in this paper. And, effect of steel sulfur content on CGR was less pronounced under low-frequency loading (e.g., ν ≤ 4×10-3 Hz) and low-flow, oxidizing (e.g., ECP = 100-200mVSHE) BWR/normal water chemistry (NWC) conditions.
After mean crack lengths of various test specimens were evaluated using a specific electrochemical oxide removal method (ENDOX treatment), many CGR data from this study were observed to be comparable with those obtained from some well-known CGR prediction models for BWR environments except in the hydrogen water chemistry (HWC) condition. However, the current CF CGR data with a low loading frequency (ν = 4×10-4 Hz) were not bounded by the model developed by Eason. Additionally, most of our SCC CGR data cannot be encompassed by the MPA Stuttgart models.

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