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 | 千瓦級微流... 千瓦級微流道蒸發器效能提升與熱交換器設計測試應用於積體化甲醇重組系統之熱管理 (Enhancing the Efficiency of Kilowatt-Scale Microchannel Evaporators and Applying Heat Exchanger Design and Testing in Integrated Methanol Reformer Systems for Thermal Management) | NTHU NDLTD | 碩 | 2.00 |
甲醇水蒸氣重組系統(Methanol-Water vapor Reforming system)、千瓦級微流道蒸發器(Kilowatt-Level Microchannel Evaporator)、雙相流沸騰熱傳(Two-phase flow boiling heat transfer)、熱交換器(Heat Exchanger) 甲醇水蒸氣... | ||||
| 112 | CFD沸騰... CFD沸騰熱傳應用於AB-BNCT靶材熱管理之模式建立與校驗 (Development and Validation of CFD Boiling Heat Transfer Application for Heat Management in AB-BNCT Target) | NTHU NDLTD | 碩 | 1.91 |
熱管理(thermal management)、CFD 沸騰熱傳模式(CFD boiling heat transfer model)、加速器型硼中子捕獲治療(AB-BNCT)、熱變形(thermal deformation) 熱管理(t... | ||||
| 112 | 螺旋管熱交... 螺旋管熱交換器管側沸騰熱傳數值模擬分析 (Numerical simulation analysis of tube side boiling heat transfer in helical coil tube heat exchanger) | NTHU NDLTD | 碩 | 2.43 |
螺旋管(helical coil tube)、螺旋管熱交換器(helical coil heat exchanger)、沸騰熱傳(boiling heat transfer) 螺旋管(h... | ||||
| 111 | 高效能輕重... 高效能輕重量100W圓型磷酸燃料電池堆系統優化與積體化 (Optimization and integration of high efficiency and light weight 100W phosphoric acid fuel cell stack system) | NTHU NDLTD | 碩 | 1.99 |
磷酸燃料電池(Phosphoric acid fuel cell)、甲醇蒸氣重組系統整合(Methanol Vapor Reforming System Integration)、對向流(counter flow)、燃料電池堆叠(fuel cell stacking) 磷酸燃料電... | ||||
| 111 | 高放處置設... 高放處置設施熱傳-水力耦合模式建立與平行驗證分析 (Developement and Assessment of Thermal-Hydraulic Coupling Models for Final Disposal of High Level Waste) | NTHU NDLTD | 碩 | 1.91 |
用過核子燃料(Spent Nuclear Fuel)、深地層處置(Deep Geological Disposal)、熱傳-水力耦合分析(Thermal-Hydraulic Coupling Analysis)、平行驗證(Validation)、靈敏度分析(Sensitivity Analysis) 用過核子燃... | ||||
| 111 | 核一廠低放... 核一廠低放射性廢棄物貯存庫T-BOX與廠房熱流評估 (Thermal Hydraulics Assessments of Low-Level Waste Container T-BOX and Storage Building at Chinshan Nuclear Plant) | NTHU NDLTD | 碩 | 1.91 |
低放射性廢棄物(Low-level waste)、第一核能發電廠(Chinshan nuclear plant)、T-BOX(T-BOX)、CFD(CFD) 低放射性廢... | ||||
| 110 | 高放最終處... 高放最終處置設施CFD模式建立暨熱傳-水力耦合分析 (Establish CFD model and analyze Thermal-Hydraulic Coupling for disposal facility of high-level radioactive wastes.) | NTHU NDLTD | 碩 | 1.95 |
用過核子燃料(SNFD)、深地層處置(deep geologic disposal)、等效模式(equivalent model)、多處置孔(multiple disposal hole)、熱傳-水力耦合分析(thermal-hydraulic coupling) 用過核子燃... | ||||
| 110 | 高放處置設... 高放處置設施之熱傳模式驗證與全場域分析 (Validation and Full-field Analysis of Heat Transfer Models for High Level Radioactive Waste Disposal Facility) | NTHU NDLTD | 碩 | 1.95 |
高放射性廢棄物(Highly radioactive waste)、深地層處置(Deep Geological Disposal)、等效熱傳導係數(Effective heat transfer coefficient)、全場域熱傳分析(Full field heat transfer analysis) 高放射性廢... | ||||
| 110 | 高放處置設... 高放處置設施熱力水力耦合模式建立與驗證 (Establishment and Verification of Thermal-Hydraulic Coupling Model for High-level Radioactive Disposal.) | NTHU NDLTD | 碩 | 1.95 |
地下水流方程式(Porous media materials)、多孔介質材料(Richards’ equation)、理查茲方程式(Variable saturation flow)、變飽和流動(Storage term)、存儲項(undefined) 地下水流方... | ||||
| 110 | 利用MEL... 利用MELCOR程式建立國聖電廠嚴重事故模式及事故案例平行驗證 (Establish Severe Accident MELCOR Models of Kuosheng Nuclear Power Plant and Parallel Validation of Accident Sequences) | NTHU NDLTD | 碩 | 2.57 |
MELCOR(MELCOR)、MAAP5(MAAP5)、喪失冷卻水事故(LOCA)、電廠全黑事故(Station Blackout accident) MELCO... | ||||
| 109 | 高放處置工... 高放處置工程障壁熱傳模式建立與平行驗證分析 (Establishment and Verification Analysis of Heat Transfer Mode of High-level Radioactive Disposal Engineered Barrier) | NTHU NDLTD | 碩 | 1.99 |
工程壁障(Barrier)、熱傳分析(Establishment)、高放(Verification)、平行驗證(Radioactive) 工程壁障(... | ||||
| 109 | 利用MEL... 利用MELCOR建立馬鞍山電廠嚴重事故模式與結果分析 (Establish Maanshan Nuclear Power Station severe accident model using MELCOR) | NTHU NDLTD | 碩 | 1.94 |
核電廠嚴重事故模擬軟體(MELCOR)、喪失冷卻水事故(MAAP5)、電廠全黑事故(LOCA) 核電廠嚴重... | ||||
| 108 | MUSIC... MUSIC演算法與MAAP5程式於核三廠破管事件定位與分析之研究 (LOCA localization and analysis for Maanshan nuclear power plant with MUSIC and MAAP 5 code) | NTHU NDLTD | 碩 | 2.00 |
MAAP(MAAP)、破管事件(LOCA)、核三廠(undefined) MAAP(... | ||||
| 108 | 馬鞍山電廠... 馬鞍山電廠 MELCOR 2.2 版程式建立與電廠全黑事故分析 (Building MELCOR 2.2 Input Deck of Maanshan Nuclear Power Plant and Analyses of Station Blackout Accident) | NTHU NDLTD | 碩 | 2.00 |
電廠全黑事故(Station Blackout Accident)、MELCOR 2.2(MELCOR 2.2) 電廠全黑事... | ||||
| 108 | 蒸汽產生器... 蒸汽產生器管束壓力限值分析與可靠度評估 (Evaluation of the structural reliability and limitation of pressure for a steam generator tube) | NTHU NDLTD | 碩 | 2.00 |
擴展有限元素法(XFEM)、破壞力學(FractureMechanics)、蒸汽產生器管束(SteamGeneratortube)、應力腐蝕裂紋(PWSCC) 擴展有限元... | ||||
| 108 | 馬鞍山電廠... 馬鞍山電廠主蒸汽管路破裂事故分析之RELAP5/SNAP/DAKOTA模式建立與應用 (The Development and Application of Maanshan RELAP5/SNAP/DAKOTA Model in MSLB Analysis) | NTHU NDLTD | 碩 | 1.99 |
核三廠(Maanshan NPP)、主蒸汽管路破裂事故(MSLB)、不準度分析(Uncertainty analysis)、RELAP5/MOD3.3(RELAP5/MOD3.3)、DAKOTA(DAKOTA) 核三廠(M... | ||||
| 108 | 核能電廠重... 核能電廠重要組件結構可靠度與完整性研究 (The structural integrity and reliability analysis of critical component in nuclear power plant) | NTHU NDLTD | 博 | 3.90 |
結構可靠度(structural integrity)、機率破壞力學(probabilistic fracture mechanic)、壓力熱震(pressurized thermal shock) 結構可靠度... | ||||
| 107 | 向下池核沸... 向下池核沸騰的熱傳現象與汽泡機制 (The heat transfers and the bubble dynamics of downward nucleate pool boiling) | NTHU NDLTD | 碩 | 1.91 |
池核沸騰(Nucleate pool boiling)、加熱面傾斜角(Orientation angle of heating surface)、有效成核址密度(Active nucleation site density)、汽泡直徑(Bubble diameter)、汽泡頻率(Bubble frequency)、汽泡速度(Bubble velocity)、分析模型(Analysis model) 池核沸騰(... | ||||
| 106 | 氣液雙相流... 氣液雙相流中基於紊流的新介面作用力機制：模式開發、實驗驗證與數值模擬 (The New Mechanism of Interfacial Force Based on Turbulence in the Gas-liquid Two-phase flow: Modeling, Experiment and Simulation) | NTHU NDLTD | 碩逕博 | 5.00 |
雙相流(Two phase flow)、雙流體模型(Two-fluid model)、介面作用力(Interfacial force)、紊流(Turbulent flow)、CFD模擬(CFD simulation) 雙相流(T... | ||||
| 106 | CFD研究... CFD研究攪混翼結構參數對棒束通道流動與傳熱特性之影響效應 (CFD Investigating Effects of the Structure Parameters of the Mixing Vane on the Flow and Heat Transfer Characteristics for Rod Bundle Channels) | NTHU NDLTD | 碩(外籍生) | 1.00 |
CFD(CFD)、棒束通道(Rod bundle channel)、定位格架(Spacer grid)、攪混翼(Mixing vane)、結構參數(Structural parameters) CFD(C... | ||||
| 106 | T型管內熱... T型管內熱混合與熱振盪CFD模擬分析 (Analysis of Thermal mixing and Thermal striping in T-junction based on CFD simulation) | NTHU NDLTD | 碩(外籍生) | 1.00 |
T型管(T-junction)、熱混合(Thermal mixing)、熱振盪(Thermal striping)、回流(Reverse flow) T型管(T... | ||||
| 106 | 不同加熱傾... 不同加熱傾角對於池核沸騰的影響 (Effects of Heater Surface Orientation on Nucleate Pool Boiling Heat Transfer) | NTHU NDLTD | 碩 | 1.91 |
核沸騰(Nucleate boiling)、傾斜角(Orientation)、有效成核址密度(Nucleation site density)、汽泡脫離直徑(Bubble departure diameter)、汽泡脫離頻率(Bubble departure frequency) 核沸騰(N... | ||||
| 106 | 核電廠除役... 核電廠除役過渡階段緊要區域之鑑定與評估 (Identification of Vital Areas During Nuclear Power Plants Transitional Stage of Decommissioning) | NTHU NDLTD | 碩 | 1.91 |
緊要區鑑定(PRA)、風險評估(Vital area)、除役(Decommissioning) 緊要區鑑定... | ||||
| 106 | 馬鞍山電廠... 馬鞍山電廠 RELAP5/MOD3.3 破口喪失冷卻水事故分析 (Development of Maanshan RELAP5/MOD3.3 Model and Application of Design Basis LOCA Analysis) | NTHU NDLTD | 碩 | 1.91 |
馬鞍山電廠(Maanshan)、大破口喪失冷卻水(LBLOCA)、小破口喪失冷卻水(SBLOCA)、不準度分析(Uncertainty analysis)、RELAP5(RELAP5) 馬鞍山電廠... | ||||
| 105 | 高溫氣冷式... 高溫氣冷式反應器中子物理與熱流分析耦合之研究 (Neutronic and Thermal-hydraulic Coupling Study on High Temperature Gas-cooled Reactor) | NTHU NDLTD | 碩 | 1.99 |
中子物理與熱流分析耦合(Neutronic and Thermal-hydraulic coupling)、高溫氣冷式反應器(Prismatic High Temperature Gas-cooled Reactor) 中子物理與... | ||||
| 105 | 垂直T型管... 垂直T型管氣泡流之CFD模式建立 (CFD model development for bubbly flow in T-junction) | NTHU NDLTD | 碩 | 2.97 |
雙相流(Two-phase flow)、T型管(T junction)、氣泡流(Bubbly flow)、數值模擬(Numerical analysis)、相分離(Phase redistribution) 雙相流(T... | ||||
| 105 | THOR受... THOR受到地震負荷下之 CFD三維池水晃蕩模擬 (The CFD simulation of three-dimensional liquid sloshing in THOR under seismic excitation) | NTHU NDLTD | 碩 | 2.97 |
THOR(THOR)、CFD(CFD)、流體體積法VOF(VOF)、地震加速度(Earthquake acceleration) THOR(... | ||||
| 105 | 利用CFD... 利用CFD評估核一廠既有乾式貯存設施應用於電廠除役之可行性 (Evaluate the feasibility of CSDSS application for nuclear facility decommissioning through CFD) | NTHU NDLTD | 碩 | 1.97 |
計算流體力學(DSS)、乾式貯存系統(CFD) 計算流體力... | ||||
| 105 | 燃料護套鋯... 燃料護套鋯水反應之CFD模式發展與應用研究 (Development Application Study CFD Model on Zirconium-Water Reaction of Fuel cladding) | NTHU NDLTD | 碩 | 1.97 |
鋯水反應(Zircaloy/steam reaction)、CFD核能安全分析(Rod bundles)、燃料管束(CFD)、計算流體力學(Uncertainty analysis)、不準度分析(LOCA) 鋯水反應(... | ||||
| 105 | 雙相流於垂... 雙相流於垂直T型管之相分離實驗研究與空泡分率之測量方法 (The Separation of Two-Phase Flow Through a Vertical T-junction and the Measurement of Void Fraction) | NTHU NDLTD | 碩 | 1.97 |
T型管(T-junction)、雙相流(two-phase flow)、空泡分率(void fraction)、LOCA(LOCA)、分流(phase separation)、相分離(undefined) T型管(T... | ||||
| 105 | 應力分析與... 應力分析與CFD雙向耦合之流沖振動(FIV)模式建立 (Developing Two-way Coupling Method of CFD/Stress Analysis for Flow-induced Vibration) | NTHU NDLTD | 碩 | 1.97 |
流沖振動(Fluid-induced vibration)、單向流固耦合(One way FSI)、雙向流固耦合(Two way FSI) 流沖振動(... | ||||
| 104 | T型管單相... T型管單相流於不同流速比下混合情況之實驗研究 (Experimental Study on Mixing in Single Phase Fluid with Varied Velocity Ratio of T-junction Pipe) | NTHU NDLTD | 碩 | 暫無口試日期 |
T型管(T-junction)、熱混合(Thermal mixing)、回流(Reverse flow) T型管(T... | ||||
| 104 | 六角柱型高... 六角柱型高溫氣冷式反應器爐心功率分佈計算與爐心溫度分佈熱流計算耦合模式之建立 (Establishment of Coupling Model between Core Calculations and Thermal-Hydraulic Calculations for Prismatic-Type High Temperature Gas-Cooled Reactor) | NTHU NDLTD | 碩 | 暫無口試日期 |
高溫氣冷式反應器(high temperature gas-cooled reactor)、爐心耦合計算模式建立(coupling model for core calculation) 高溫氣冷式... | ||||
| 104 | 壓水式反應... 壓水式反應器壓熱震之CFD技術建立與應用 (ESTABLISHMENT AND APPLICATION OF CFD TO INVESTIGATE THE PTS CHARACTERISTIC BEHAVIOR IN PRESSURIZED WATER REACTOR) | NTHU NDLTD | 碩逕博 | 暫無口試日期 |
壓熱震(PTS)、壓水式反應器(PWR)、計算流體力學(CFD)、PIRT(PIRT)、V&V(Verification and Validation)、MSLB(SO-1)、SO-1(MSLB)、SBLOCA(SBLOCA) 壓熱震(P... | ||||
| 104 | 核能電廠反... 核能電廠反應器壓力槽腹帶區壓力熱震結構可靠度評估 (Structure reliability assessment of PWR pressure vessel subjected to pressurized thermal shock events) | NTHU NDLTD | 碩 | 暫無口試日期 |
壓力熱震(Pressurized thermal shock)、機率破裂力學(Probabilistic fracture mechanics)、化學組成變化(Chemical content variation)、煙雲效應(Plume effect) 壓力熱震(... | ||||
| 103 | 利用計算流... 利用計算流體力學分析壓水式反應器頂蓋區域熱水流特性 (CFD Investigation for the Dome Section of PWR) | NTHU NDLTD | 碩 | 暫無口試日期 |
計算流體力學(CFD)、壓水式反應器(PWR)、應力(stress) 計算流體力... | ||||
| 103 | 放射核種於... 放射核種於核電廠地下水安全分析之傳輸特性研究 (The safety analysis of radionuclides transportation characteristics through groundwater of nuclear power plant) | NTHU NDLTD | 碩 | 暫無口試日期 |
核能電廠(Nuclear Power Plant)、地下水(groundwater)、環境汙染(contamination) 核能電廠(... | ||||
| 103 | 核一乾貯系... 核一乾貯系統熱流分析技術發展 (Development of Thermal-Hydraulic Analysis Methodology of Dry-Storage System for Chinshan Nuclear Power Plant) | NTHU NDLTD | 碩 | 暫無口試日期 |
核一乾式貯存、計算流體力學 核一乾式貯... | ||||
| 103 | 向下加熱式... 向下加熱式表面沸騰熱傳之實驗研究 (Experimental Study of Boiling Heat Transfer Under a Downward-Facing Heated Surface) | NTHU NDLTD | 碩 | 暫無口試日期 |
向下加熱(Downward-Facing)、沸騰(Boiling)、對流(Convection)、汽泡(Bubble)、次冷態水(Coolant Flow) 向下加熱(... | ||||
| 102 | CFD燃料... CFD燃料組件分析模式誤差之研究 (Investigating the simulation errors for CFD models in the fuel bundle) | NTHU NDLTD | 碩 | 暫無口試日期 |
燃料管束(Rod bundles)、計算流體力學(CFD)、格點誤差(Mesh Error)、模式誤差(Model Error)、不準度分析(Uncertainty analysis) 燃料管束(... | ||||
| 102 | 利用計算流... 利用計算流體力學分析壓水式反應器之壓熱震熱流特性之研究 (CFD Investigating the Pressure Thermal Shock Behavior in Pressurized Water Reactor) | NTHU NDLTD | 碩 | 暫無口試日期 |
壓熱震(PTS)、壓水式反應器(CFD)、計算流體力學(PWR) 壓熱震(P... | ||||
| 102 | 利用CFD... 利用CFD模式研究小風機流場與聲場之特性 (Investigations on the flow field and acoustic characteristics using CFD model for small-scale wind turbines) | NTHU NDLTD | 碩 | 暫無口試日期 |
水平軸風力發電機、垂直軸風力發電機、紊流模式、FW-H方程式、噪音 水平軸風力... | ||||
| 101 | 馬鞍山電廠... 馬鞍山電廠用過燃料池之暫態熱水流分析 (Transient Thermal Hydraulic Analysis for Spent Fuel Pool of Maanshan Nuclear Power Plant) | NTHU NDLTD | 碩 | 暫無口試日期 |
計算流體力學(CFD)、燃料棒束(fuel bundle)、自然對流(natural circulation)、用過燃料池(spent fuel pool) 計算流體力... | ||||
| 101 | MAAP5... MAAP5模擬國聖核能電廠斷然處置安全評估的靈敏度分析 (Sensitivity Analysis of Ultimate Response Guideline for Kuosheng Nuclear Power Plant with MAAP5) | NTHU NDLTD | 碩 | 暫無口試日期 |
國聖電廠、MAAP5、斷然處置、嚴重事故 國聖電廠、... |