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Materials Ageing in Light-Water Reactors: Handbook of Destructive Assays

為了解決Light tubes的問題，作者Cattant, François 這樣論述：

François Cattant graduated in chemical engineering in 1974 and joined Electricity of France (EDF) in 1975 as a chemical engineer in the Plant Operation Division working on the water and steam conditioning of power plants. Two years later, he moved to the hot laboratory at the Chinon Nuclear Power Pl

ant to examine failures and do root cause analysis of gas-cooled reactor components, including fuel. In 1980, he became the manager of a regional section for water and steam chemistry, chemical cleaning and non-destructive examination in fossil stations. He returned to the Chinon hot laboratory 3 ye

ars later where he continued to focus on failure root cause analysis of irradiated or contaminated components, monitoring of reactor pressure vessel (RPV) irradiation programs, examination of steam generator tubes, RPV head penetrations, split pins, pressurizer nozzles, valves, reactor cooling syste

m cast elbows, piping, fuel bundle and rods, rod cluster control assemblies, and much more.During 1995-1998, he was assigned as an expatriate engineer to the Nuclear Maintenance Applications Center of the Electric Power Research Institute in the USA where he worked on nuclear plant maintenance issue

s. While at EPRI, he also participated as an outside expert on the examination of Ringhals 3 retired steam generator. Returning back in France in 1998, François joined EDF R&D Materials and Mechanics of Components Department as a scientific advisor and senior engineer. His work involved chemistry, c

orrosion, and metallurgy with special attention to primary water chemistry, source term reduction, primary water corrosion, corrosion mitigation and repair, fuel cleaning and innovation strategies. He continued to serve as the EDF representative to the EPRI’s Materials Reliability Program. In this c

apacity, he participated in several destructive examinations such as North Anna Unit 2 RPV head penetrations, South Texas Project Unit 1 Bottom Mounted Instrumentation, Braidwood Unit 1 pressurizer heater #52 and San Onofre Unit 3 CEDM #64. From 2004 to 2008, he was the president of the ＂Materials,

Non-Destructive Testing and Chemistry＂ section of the ＂French Nuclear Energy Society＂, and from 2008 to 2009, he was in charge of the International Partnerships of the Materials Ageing Institute (MAI). Subsequent to his retirement from EDF in 2009, he was commissioned by the MAI to collect details a

nd produce summaries of destructive examinations performed on failures in light-water reactor components in France, USA, Japan, and Sweden which have now been compiled in this unique handbook. In 2014, the French Nuclear Energy Society awarded its ＂Grand Prix＂ to this ＂Handbook of Destructive Assays

＂. Ten years later, the MAI asked him to update this handbook, with both domestic and international recent field experience.

Light tubes進入發燒排行的影片

智能影像運輸系統於輔助、維護與監控應用

為了解決Light tubes的問題，作者呂安豐 這樣論述：

人工智慧的進步以更精密的方式迅速改變了交通系統。智慧交通系統結合行人、道路及車輛相關資訊，以提供更高的安全性、效率和舒適性。智慧交通系統中的每個元素相互牽制並都應被保留及作後續的改善。電腦視覺的最新進展在許多方面豐富了機器感知的能力。因此，本研究旨在提出一種基於智能視覺的方法，以加強智慧交通系統在協助、維護和監控方面的效果。在輔助方面，本研究著重於駕駛睡意偵測系統和交通場景分割，提出基於深度學習的即時駕駛睡意偵測系統，試圖提高極端場景下的睡意檢測品質。在交通場景分割中，利用了邊緣和特徵級別過濾方式，以達到更好的切割效果。此外，本論文提出基於知識轉移的方法來生成一個強大且有效的模型。在維護方面

，本論文提出經改良的道路裂紋檢測方法，著重於裂紋細化和具自動資源映射的高效檢測器。最後，監控方面基於視訊濃縮，能夠生成短、密集且緊湊的視頻。整體而言，上述六項成果在智慧交通系統的進步方面皆具有巨大的潛力，與文獻裏現有方法相比，本論文所提出的方法在各項指標上皆有突出的表現。

Light Intensity Modulation in Hydrogen and Deuterium Discharge Tubes

為了解決Light tubes的問題，作者Jones, Donald Eugene 這樣論述：

水化學控制對於壓水式反應器一次側水環境 600合金與316L不銹鋼的應力腐蝕龜裂影響之研究

為了解決Light tubes的問題，作者施湘鈴 這樣論述：

鎳基合金600 (Alloy 600)與沃斯田鐵不銹鋼316L (SS 316L)為壓水式反應器(Pressurized Water Reactor, PWR)常見的結構組件材料，然而在電廠長期運轉下，結構組件腐蝕劣化問題層出不窮，如一次側冷卻水應力腐蝕龜裂(Primary Water Stress Corrosion Cracking, PWSCC)。為減緩腐蝕問題，各國電廠對於PWR進行了適當的水化學調控，如添加氫氣、控制pH值、硼酸濃度與氫氧化鋰濃度等。添加氫氣用以降低水環境因輻射分解反應而提高的氧化性，並減緩組件材料劣化，然而在目前EPRI規範的溶氫濃度25-50 cc⁄kg H2O

與運轉溫度320-360℃下，仍有PWSCC發生，因此各國核電廠考慮調整溶氫濃度至5 cc/kg H2O以下，或75 cc/kg H2O以上。此外，於水迴路中添加硼酸以控制中子反應度，添加氫氧化鋰則用於平衡水環境的pH值。但隨著燃料週期的燃耗，硼濃度逐漸下降，氫氧化鋰濃度也需有所調整。藉由溶氫(dissolved hydrogen, DH)濃度與pH值的調控，可使材料避開Ni/NiO的相轉換點，進而減緩PWSCC發生。因此本研究將探討燃料週期初期(Beginning of Cycle, BOC)與末期(End of Cycle, EOC)水環境在溶氫濃度降低至5 cc/kg H2O的條件下，對

於Alloy 600與SS 316L所造成的影響。本研究透過模擬PWR一次側水環境，對於Alloy 600與SS 316L進行慢應變速率拉伸試驗(Slow Strain Rate Test, SSRT)。實驗先將Alloy 600與SS 316L試棒進行固溶退火熱處理(SA)後，再分別進行單一階段時效處理(TT)與敏化熱處理(SEN)並預長氧化膜。而後模擬燃料週期初期與末期，在320℃與溶氫濃度為5 cc/kg H2O的水環境下進行SSRT試驗，分析材料應力腐蝕龜裂(Stress Corrosion Cracking, SCC)行為，並對於試棒破斷面與表面氧化膜形貌進行觀察與分析。實驗結果顯示

，對於Alloy 600而言，TT試棒在1200 ppm B + 3.5 ppm Li溶氫條件下展現最差的機械性質，但無論是除氧或溶氫環境，Alloy 600都表現出較低的SCC敏感性。而SS 316L SEN試棒在300 ppm B + 1 ppm Li溶氫條件下的最大抗拉強度(Ultimate Tensile Strength, UTS)與降伏強度(Yield Strength, YS)表現最差，然而實驗結果顯示溶氫可有效降低SEN試棒的SCC敏感性。Alloy 600表面氧化膜主要由尖晶石氧化物(spinel oxide) NiFe2O4、Cr2O3與NiO所構成，SS 316L的表面氧

化膜則以α-Fe2O3、γ-Fe2O3、尖晶石氧化物NiFe2O4與Fe3O4為主。