Labook

清大研究所畢業論文與畢業時長統計

陳紹文(博: 6.46 years、碩: 2.09 years)

政府計畫(GRB),建議「依年度遞減排序」,以查看最新的研究方向。

畢業學年度論文標題連結學位畢業時長(years)
關鍵字
112
利用集群法...
利用集群法與監督式學習進行3×3模擬棒束雙相流譜分群分析 (Use Clustering Method and Supervised Learning to Complete Two-Phase Flow Regime Classification Analysis of 3×3 Simulated Rod Bundle)
NTHU
無口試日期
棒束雙相流(Rod-bundle two-phase flow)、流譜分群(Flow regime)、空泡分率(Void fraction)、集群分析(Clustering analysis)、卷積神經網路(Convolution neural network)
棒束雙相流...
111
機器學習應...
機器學習應用於超臨界流體熱傳惡化之研究與探討 (The Investigation of Heat Transfer Deterioration in Supercritical Fluids by Using Machine Learning Methods)
NTHU
NDLTD
1.98
超臨界流體(supercritical fluids)、熱傳惡化(heat transfer deterioration)、機器學習(machine learning)、肇始熱通率(heat flux onset)
超臨界流體...
111
監督式與非...
監督式與非監督式學習應用於強制震動矩形管中汽液雙相流之流譜鑑別 (Supervised and Unsupervised Learning Applied to Flow Regime Identification of Air-water Two-phase Flow in a Forced-vibration Rectangular Tube)
NTHU
NDLTD
1.98
雙相流(Two-phase flow)、空泡分率(Void fraction)、流譜(Regime analysis)、聚類分析(Clustering analysis)、卷積神經網路(Convolutional Neural Network)、機器學習(Machine learning)、簡諧震動(Harmonic vibration)
雙相流(T...
110
利用TRA...
利用TRACE程式建立國聖電廠除役過渡階段反應爐開蓋模式與安全分析 (Utilizing TRACE to Establish Kuosheng Nuclear Power Plant in Decommissioning Transition Phase and Apply in Safety Analysis)
NTHU
NDLTD
1.97
國聖電廠(Kuosheng nuclear power plant)、除役過渡階段(Loss of cooling accident)、喪失冷卻(Loss of coolant accident)、喪失冷卻水(Decommissioning transition phase)、安全分析(Safety analysis)
國聖電廠(...
110
3x3模擬...
3x3模擬棒束氣液雙相流之非監督式學習流譜鑑別 (Flow Regime Identification by Unsupervised Learning for Air-Water Two-Phase Flow in a 3x3 Simulated Rod Bundle)
NTHU
NDLTD
1.98
模擬棒束(rod bundle geometry)、氣液雙相流(air-water two phase flow)、空泡分率(void fraction)、累積機率密度分佈圖(cumulative distribution function)、機器學習(machine learning)
模擬棒束(...
110
MELCO...
MELCOR潛變破裂研究分析與國際間SAMG嚴重事故管理指引探討 (Analysis of Creep Rupture with MELCOR and Discussion on International Severe Accident Management Guidelines)
NTHU
NDLTD
1.97
電廠全黑(Station Blackout)、自然循環(Natural Circulation)、潛變破裂(Creep Rupture)、MELCOR2.2(MELCOR2.2)、SAMG(SAMG)
電廠全黑(...
110
超音波振動...
超音波振動對池狀態不同條件之熱傳強化與臨界熱通量影響研究 (Experimental Study of Heat Transfer Enhancement and Critical Heat Flux in Pool at Different Testing Conditions under Ultrasonic Vibration)
NTHU
NDLTD
1.96
超音波震盪(Ultrasonic vibration)、熱傳增益效果(Heat transfer gain effect)、電熱絲(Heating wire)、波長(Wavelength)、聲壓(Sound pressure)、臨界熱通量(Critical heat flux)
超音波震盪...
110
金山核電廠...
金山核電廠TRACE/PARCS模式之圍阻體系統及爐心中子動力學拓展與應用 (The Development and Application of Containment System and Core Neutron Kinetics for Chinshan Nuclear Power Plant TRACE/PARCS Model)
NTHU
NDLTD
7.44
TRACE(TRACE)、PARCS(PARCS)、CONTAN(CONTAN)、金山核電廠(Chinshan Nuclear Power Plant)、電廠全黑(SBO)、喪失冷卻水事件(LOCA)、斷然處置措施(URG)
TRACE...
109
垂直振動矩...
垂直振動矩形管之雙相流動態特性分析與集群法流譜鑑別研究 (Dynamic Characteristics Analysis and Flow Regime Identification by Clustering Methods for Two-Phase Flow in a Rectangular Tube under Vertical Vibration)
NTHU
NDLTD
1.99
雙相流(Two-phase flow)、空泡分率(Void fraction)、流譜(Flow regime)、集群分析(Cluster analysis)、振動(Vibration)
雙相流(T...
109
垂直上升氣...
垂直上升氣液雙相流之流譜動態分析與鑑別 (Flow Regime Dynamic Analysis and Identification for Vertical Upward Air-Water Two-Phase Flow)
NTHU
NDLTD
1.99
雙相流流譜(two-phase flow regimes)、動態分析(dynamic analysis)、空泡分率(void fraction)、機械學習(machine learning)
雙相流流譜...
109
利用TRA...
利用TRACE程式建立金山電廠除役過渡階段反應器開蓋模式與安全分析 (Utilizing TRACE to Establish Chinshan Integrated Spent Fuel Pool Model in Decommissioning Transition Phase and Apply in Safety Analysis)
NTHU
NDLTD
1.98
金山電廠(Chinshan nuclear power plant)、除役過渡階段(loss of coolant accident)、開蓋模式(decommissioning transition phase)、安全分析(safety analysis)
金山電廠(...
108
利用TRA...
利用TRACE程式建立金山電廠除役期間用過燃料池模式與安全分析 (Use of TRACE to Establish Chinshan Spent Fuel Pool Model in Decommission Phase and Apply in Safety Analysis)
NTHU
NDLTD
1.99
核能一廠(Chinshan spent fuel pool)、除役階段(Severe accident)、用過燃料池(Decommission Phase)、嚴重事故(undefined)
核能一廠(...
108
利用MEL...
利用MELCOR2.2程式探討核一廠除役階段用過燃料池完全失水下鋯合金護套溫升現象 (Temperature Rise of Zirconium Alloy Cladding under LOCA at Decommissioning Chinshan BWR Spent Fuel Pool by MELCOR2.2)
NTHU
NDLTD
1.99
MELCOR2.2/SNAP(MELCOR2.2/SNAP)、核一廠(Decommissioning)、除役階段(Spent Fuel Pool)、用過燃料池(Chinshan Nuclear Power Plant)、喪失冷卻水事故(Emergency Planning)、緊急計畫(undefined)
MELCO...
108
強制垂直振...
強制垂直振動對平行通道沸騰雙相流之影響研究 (The Influence of Forced Vertical Vibration on Boiling Two-phase Flow in Parallel-Channel)
NTHU
NDLTD
1.98
平行通道(Parallel-channel)、振動(Vibration)、頻率(Frequency)、不穩定(Instability)、穩定性邊界(Stable boundary)
平行通道(...
108
3 × 3...
3 × 3 模擬棒束之汽液雙相流動態特性分析與流譜鑑別 (Dynamic Analysis and Flow Regime Identification for Air-Water Two-Phase Flow in a 3 × 3 Rod Bundle)
NTHU
NDLTD
1.98
模擬棒束(rod bundle geometry)、汽液雙相流(air-water two phase flow)、空泡分率(void fraction)、累積機率密度分佈圖(cumulative probability density function)、自組織映射(self-organizing map)、類神經網路(artificial neural network)
模擬棒束(...
108
超音波振動...
超音波振動對池狀態之熱傳強化研究 (Experimental Study of Heat Transfer Enhancement in Pool under Ultrasonic Vibration)
NTHU
NDLTD
1.98
超音波震盪(ultrasonic vibration)、熱傳增強(heat transfer enhancement)、聲壓(sound pressure)
超音波震盪...
108
共晶熔融物...
共晶熔融物質Bi2O3-WO3淬冷之實驗研究 (Experimental investigation on the quenching of eutectic molten materials (Bi2O3-WO3))
NTHU
NDLTD
2.45
共晶物質(eutectic material)、熔融物質(molten material)、淬冷(quenching)、多相流(multiphase flow)
共晶物質(...
107
以TRAC...
以TRACE程式進行馬鞍山電廠在不同塞管率下之全黑事故與救援程序分析 (Analysis of Maanshan Station Blackout Accident and Rescue Procedures Under Different Tube Plugging Situations with TRACE)
NTHU
NDLTD
1.99
馬鞍山電廠(MaanshanNPP)、電廠全黑(SBO)、斷然處置(URG)、塞管率(FLEX)、壓水式電廠(TubePlugging)
馬鞍山電廠...
107
建立MEL...
建立MELCOR2.2核三廠全黑之管路潛變破裂事故分析模式 (Analysis of Maanshan Nuclear Power Plant in ELAP Condition with Hot Leg Creep Rupture Using MELCOR2.2)
NTHU
NDLTD
1.99
MELCOR(MELCOR)、馬鞍山電廠(MaanshanNPP)、潛變破裂(creeprupture)
MELCO...
107
流動方向對...
流動方向對迷你流道內超臨界二氧化碳熱傳效應之實驗研究 (Experimental Investigation on the Effects of Flow Direction on Convection of Supercritical Carbon Dioxide in a Miniature Tube)
NTHU
NDLTD
1.99
超臨界(Supercritical)、二氧化碳(Carbon-dioxide)、熱傳(Heat-transfer)、流向效應(Flow-directions)
超臨界(S...
107
以脈衝式熱...
以脈衝式熱管做爲增加太陽能模組效率暨太陽能熱水供應之研究 (Improve the Efficiency of Solar Panel and Get Sun-Heated Water by Pulsed Heat Pipes)
NTHU
NDLTD
1.98
矽基太陽能電池(Silicon-based solar panel)、脈衝式熱管(Pulsed heat pipe)、相變化材料(Phase-changed material)、潛熱(Latent heat)、太陽能熱水器(Solar water heater)
矽基太陽能...
107
脈衝式熱管...
脈衝式熱管應用在模擬電動車鋰電池包之研究 (The Research and Simulation for the Lithium Battery Electric Vehicle by Using Pulsating Heat Pipe)
NTHU
NDLTD
1.98
脈衝式熱管(Pulsating Heat Pipe)、相變化材料(Phase Change Material)、電池包(battery pack)
脈衝式熱管...
107
薄型散熱材...
薄型散熱材料之熱擴散率量測技術研究 (The Measurement Technology Development of the Thermal Diffusivity of Thin Heat Dissipation Material)
NTHU
NDLTD
1.98
熱擴散率(Angstrom method)、石墨片(Thermal Diffusivity)、均溫板(graphite sheet)、熱管(vapor chamber)
熱擴散率(...
106
MELCO...
MELCOR2.2程式於沸水式反應器 嚴重事故分析之模式建立與應用 (The Establishment and Applications of MELCOR2.2 in BWR Severe Accident Analysis)
NTHU
NDLTD
碩逕博(提早入學)5.48
嚴重事故(Severe accident)、MELCOR2.2(MELCOR)、金山電廠(Chinshan NPP)、國聖電廠(Kuosheng NPP)、氫氣行為分析(hydrogen behaviors)、類福島(Fukushima-like)
嚴重事故(...
106
利用TRA...
利用TRACE與FRAPTRAN程式分析馬鞍山電廠全黑事故與喪失冷卻水事故之核燃料行為 (Fuel Rod Behavior Analysis for Maanshan Nuclear Power Plant under Loss of Coolant Accident and Station Blackout Conditions)
NTHU
NDLTD
1.98
壓水式(PWR)、TRACE(TRACE)、FRAPTRAN(FRAPTRAN)、電廠全黑(SBO)、破口喪失冷卻水事故(LOCA)
壓水式(P...
106
核電廠控制...
核電廠控制室適居性分析方法論之建立與應用 (Establishment and Application of Analysis Methodology of Control Room Habitability in Nuclear Power Plant)
NTHU
NDLTD
1.98
控制室(control room)、適居性(Habitability)、方法論(methodology)、SNAP(SNAP)、RADTRAD(RADTRAD)、HABIT(HABIT)、ALOHA(ALOHA)
控制室(c...
106
散佈型氣泡...
散佈型氣泡流之流譜鑑別與特性分析 (Flow Regime Identification and Characteristic Analysis of Dispersed Bubbly Two-Phase Flow)
NTHU
NDLTD
1.98
散佈型氣泡流(dispersed bubbly flow)、空泡分率(void fraction)、機率密度分佈圖(probability density function)
散佈型氣泡...
106
振動特性對...
振動特性對矩形管雙相流之影響研究 (The Influence of Vibration Characteristics on Two-phase Flow in Rectangular Channel)
NTHU
NDLTD
1.98
空泡分率(Void fraction)、振動(Vibration)、頻率(Frequency)、震幅(Amplitude)、流譜(Flow pattern)
空泡分率(...
106
核燃料護套...
核燃料護套行為評估方法論建立與應用 (The Development and Application of the Nuclear Fuel Cladding Behavior Evaluation Methodology)
NTHU
NDLTD
5.49
核燃料行為分析(Fuel cladding performance analysis)、FRAPCON(FRAPCON)、FRAPTRAN(FRAPTRAN)
核燃料行為...
105
馬鞍山電廠...
馬鞍山電廠MELCOR2.1模式建立與嚴重事故分析 (Establishment of Maanshan Nuclear Power Plant MELCOR 2.1 Model and Severe Accident Analysis)
NTHU
NDLTD
1.97
MELCOR(SBO)、電廠全黑事故(MELCOR)、嚴重事故分析(Severe Accident Analysis)
MELCO...
105
遭受外加垂...
遭受外加垂直震動下單一沸騰通道雙相流循環 迴路之非線性動態分析 (The nonlinear dynamic analysis of a single boiling channel two-phase circulation loop under external vertical vibration condition)
NTHU
NDLTD
1.97
沸騰通道(Boiling channel)、穩定性邊界(natural frequency)、自然頻率(resonance)、共振效應(vertical acceleration)、非線性分析(nonlinear anaylsis)
沸騰通道(...
105
以TRAC...
以TRACE程式進行馬鞍山電廠嚴重事故分析與事故緩和策略之探討 (Analysis of Maanshan NPP Severe Accident and Mitigation strategy using TRACE Code)
NTHU
NDLTD
1.97
斷然處置(URG)、FLEX(FLEX)、核三廠(Maanshan)、迴流冷卻(reflux cooling)、電廠全黑(SBO)
斷然處置(...
105
雙相攪拌流...
雙相攪拌流譜訊號處理發展與特性分析 (Developing Signal Process and Characteristic Analysis of Churn Two-Phase Flow)
NTHU
NDLTD
1.95
雙相流(Two-Phase Flow)、攪拌流(Churn Flow)、空泡分率(Void Fraction)
雙相流(T...
105
矩形管雙相...
矩形管雙相流流譜與強制震動影響分析 (The Effect of Two-phase Flow Patterns in Rectangular Pipe under Forced Vibration Conditions)
NTHU
NDLTD
1.95
雙相流(Two-phase flow)、強制震動(forced vibration)、空泡分率(foid fraction)、電導度計(conductance probe)
雙相流(T...
105
沸水式反應...
沸水式反應器斷然處置措施有效性分析 (The Analysis of Effectiveness of BWR URG Strategies)
NTHU
NDLTD
1.52
斷然處置措施(URG)、沸水式核能電廠(MAAP)
斷然處置措...
104
國聖電廠T...
國聖電廠TRACE/CONTAN模式建立與應用 (The Establishment and Application of Kuosheng TRACE/CONTAN Model)
NTHU
NDLTD
無口試日期
國聖電廠(Kuosheng NPP)、圍阻體(containment)、熱水流分析(thermal hydraulic)
國聖電廠(...
104
池狀態下超...
池狀態下超音波對次冷沸騰熱傳的影響 (Experiment of Pool Subcooled Boiling Heat Transfer With and Without Ultrasonic Vibration)
NTHU
NDLTD
無口試日期
超音波(ultrasonic vibration)、池沸騰(pool boiling)、熱傳改善(heat transfer enhancement)
超音波(u...
104
龍門電廠之...
龍門電廠之TRACE/CONTAN模式建立 與斷然處置分析 (The Establishment of TRACE/CONTAN Model and Ultimate Response Guideline Analysis for Lungmen ABWR)
NTHU
NDLTD
無口試日期
斷然處置(TRACE)、主蒸汽管斷裂事故(CONTAN)
斷然處置(...
103
利用中子照...
利用中子照相觀測垂直和水平圓管內雙相流特性之可行性研究 (Feasibility study for two-phase flow characteristics in vertical and horizontal tube by neutron radiography)
NTHU
NDLTD
無口試日期
中子照相(neutron radiography)、雙向流(two-phase flow)、一維漂移通率模型(1-D Drift Flux Model)、空泡分率(Void fraction)
中子照相(...
103
中子照相應...
中子照相應用於小管徑矩形管之雙相流可視化研究 (Application of neutron radiography to visualization of two phase flows in narrow rectangular ducts)
NTHU
NDLTD
無口試日期
中子照相(two-phase flow)、雙相流(neutron radiography)
中子照相(...
103
束狀環狀流...
束狀環狀流之流譜鑑別與特性分析 (Flow Regime Identification and Characteristic Analysis of Wispy Annular Two-Phase Flow)
NTHU
NDLTD
無口試日期
雙相流(Two-phase flow)、束狀環狀流(Wispy annular flow)
雙相流(T...
103
單晶3C碳...
單晶3C碳化矽於離子輻照下隨溫度變化之膨脹效應 (The Swelling Effect of Ion Irradiated Single Crystal 3C-SiC at Various Temperature)
NTHU
NDLTD
無口試日期
碳化矽(silicon carbide)、離子輻照(ion irradiation)、膨脹效應(swelling effect)、微結構變化(microstructural change)、氦氣泡(helium bubble)
碳化矽(s...
102
金山電廠用...
金山電廠用過燃料池TRACE模式建立與應用 (The Establishment and Applications of Chinshan Spent Fuel Pool TRACE Model)
NTHU
NDLTD
無口試日期
用過燃料池(Spent fuel pool)
用過燃料池...