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 | ||||
| 111 | 量化核能三... 量化核能三廠蒸汽產生器管束破裂事故序列中運轉員緩解行為之人為失誤機率 (Human Error Probability Quantification of Operator Mitigation Actions in a Steam Generator Tube Rupture Sequence) | NTHU NDLTD | 碩 | 2.00 |
蒸汽產生器管束破裂(SGTR)、壓水式反應器(PWR)、RELAP5-3D(RELAP5 3D)、安全度評估(PSA)、不準度(Uncertainty) 蒸汽產生器... | ||||
| 111 | 核三廠嚴重... 核三廠嚴重事故處理指引新版計算輔助圖驗證 (Validation of the new version Computational Aid of Severe Accident Management Guidelines of Maanshan Nuclear Power Plant) | NTHU NDLTD | 碩 | 3.36 |
核三廠嚴重事故處理指引(Severe Accident Management Guidelines)、計算輔助圖(Computational Aid)、壓水式反應器(SECURE 2.0) 核三廠嚴重... | ||||
| 110 | 定位腸病毒... 定位腸病毒71型新穎中和抗體的結合位點 (Mapping binding sites of a novel enterovirus 71 monoclonal antibody) | NTHU NDLTD | 碩(外籍生) | 1.86 |
腸病毒(Enterovirus A71) 腸病毒(E... | ||||
| 110 | 核三廠小破... 核三廠小破口冷卻水流失事故分析：人為誤失機率量化與降溫降壓之熱流分析 (Analysis of SBLOCA in a Pressurized Water Reactor: Quantification of Human Error Probability and Thermal Hydraulic Analysis of Cooldown and Depressurization) | NTHU NDLTD | 碩 | 2.49 |
小破口冷卻水流失事故(SBLOCA)、壓水式反應器(PWR)、安全度評估(PSA)、不準度(Uncertainty)、RELAP5-3D(RELAP5-3D) 小破口冷卻... | ||||
| 109 | 核三廠機組... 核三廠機組斷然處置之洩壓注水執行策略分析 (Analysis of Depressurization and Injection Strategy in Ultimate Response Guidelines of Maanshan Nuclear Power Plant) | NTHU NDLTD | 碩 | 2.00 |
斷然處置(URG)、RELAP-3D(RELAP-3D)、核三廠(Maanshan)、電廠全黑(SBO) 斷然處置(... | ||||
| 108 | 利用MAA... 利用MAAP 5.03程式量化先進式沸水反應爐電廠全黑嚴重事故壓力槽失效不準確度 (Uncertainty Qualification of Reactor Pressure Vessel Failure Under a Severe Accident In Advanced Boiling Water Reactor With MAAP 5 Code) | NTHU NDLTD | 碩 | 2.00 |
MAAP 5(MAAP5)、不準確度量化(Uncertainty)、嚴重事故模擬(Severe Accident)、壓力槽失效(Reactor Vessel Failure) MAAP ... | ||||
| 108 | 使用MAA... 使用MAAP5程式量化嚴重事故下爐內氫氣產生量之不準度研究與爐外熔渣冷卻靈敏度分析 (Uncertainty Quantification of In-Vessel Hydrogen Generation in a Severe Accident and Sensitivity Studies on Ex-vessel Debris Cooling Using MAAP5 Code) | NTHU NDLTD | 博 | 4.77 |
MAAP5(MAAP5)、不準度(Uncertainty)、氫氣(Hydrogen)、嚴重事故(Severe Accident)、爐外熔渣冷卻(Ex-vessel Debris Coolability) MAAP5... | ||||
| 108 | 發展並評估... 發展並評估適用於猴腎細胞平台之流感疫苗全能株 (master donor virus) 於流感大流行之應用 (Development and evaluation of Vero cell-based master donor viruses (MDVs) for influenza pandemic preparedness) | NTHU NDLTD | 博 | 4.55 |
流感疫苗(influenza virus)、禽流感(influenza vaccine)、猴腎細胞(Vero cells) 流感疫苗(... | ||||
| 107 | 量化核能三... 量化核能三廠喪失廠外電源事故序列中運轉員緩解行為之人為失誤機率 (Human Error Probability Quantification of Operator Mitigation Actions in a Loss of Offsite Power Sequence) | NTHU NDLTD | 碩 | 1.98 |
喪失廠外電源事故(Loss of Offsite Power)、洩充操作(Bleed and Feed)、人為失誤機率(Human Error Probability)、爐心熔損頻率(undefined) 喪失廠外電... | ||||
| 107 | 利用桿狀病... 利用桿狀病毒平台生產H7N9流感疫苗及H5N2流感的結構分析 (Establishing baculovirus-based platforms for development of influenza H7N9 vaccines and characterizing structural biology of influenza H5 hemagglutinin) | NTHU NDLTD | 博 | 7.32 |
桿狀病毒表現系統(baculovirus expression system)、流感病毒H7N9(influenza H7N9)、流感病毒H5N2(influenza H5N2) 桿狀病毒表... | ||||
| 107 | 複雜系統可... 複雜系統可靠度分析模式應用於核電廠安全評估 (Efficient Reliability Modelling & Analysis of Complex Systems with Application to Nuclear Power Plant Safety) | NTHU NDLTD | 博 | 3.08 |
系統可靠性(System Reliability)、核電廠(Nuclear Power Plants)、複雜系統(Complex Systems)、風險評估(Risk Assessment) 系統可靠性... | ||||
| 105 | 龍門電廠斷... 龍門電廠斷然處置程序分析與事故緩解指引建立 (Analysis of Ultimate Response Guidelines of Lungmen Nuclear Power Plant) | NTHU NDLTD | 碩 | 1.97 |
龍門電廠(Lungmen Nuclear Power Station)、斷然處置程序(Ultimate Response Guidelines)、電廠全黑事故(Station Blackout) 龍門電廠(... | ||||
| 104 | 研究REL... 研究RELAP5/MOD3的虹吸破壞現象 (The Study of the Phenomenon of Siphon Break using RELAP5/MOD3) | NTHU NDLTD | 碩 | 無口試日期 |
虹吸破壞現象(siphon break)、非能動(passive)、流動特性(flow characteristic)、核能安全(nuclear safety) 虹吸破壞現... | ||||
| 104 | 核二廠RE... 核二廠RELAP5-3D輸入檔之控制系統建立與驗證 (Building the Control Systems of RELAP5-3D Input Deck of KuoSheng Nuclear Power Station) | NTHU NDLTD | 碩 | 無口試日期 |
核二廠(KuoSheng Nuclear Power Station)、控制系統(Control System)、RELAP5(RELAP5)、暫態分析(Transient analysis)、熱水流(Thermal hydraulic) 核二廠(K... | ||||
| 104 | RELAP... RELAP5與FRAPTRAN模擬國聖電廠功率提升後增壓暫態燃料護套機械性質與不準度分析 (Uncertainty Analysis of Fuel Rod Performance of Kousheng Nuclear Power Plant during Overpressurization Transient under 104.7% Power with RELAP/FRPTRAN code) | NTHU NDLTD | 碩 | 無口試日期 |
RELAP5(RELAP5)、核二廠(NPP2)、增壓暫態(overpressurization)、不準度分析(Uncertainity)、FRAPTRAN(FRAPTRAN) RELAP... | ||||
| 103 | 金山電廠用... 金山電廠用過燃料池喪失冷卻事故模擬 (Loss of Cooling Accident Simulation of Chinshan Nuclear Power Station Spent-fuel Pool) | NTHU NDLTD | 碩 | 無口試日期 |
金山電廠(Chinshan)、RELAP5(RELAP5)、MAAP5.02(MAAP5.02)、用過燃料池(spent fuel pool)、喪失冷卻事故(loss of cooling accident) 金山電廠(... | ||||
| 102 | 核一廠ME... 核一廠MELCOR程式輸入檔的建立與電廠全黑嚴重事故分析 (Building MELCOR Input Deck of Chinshan Nuclear Power Station and Analyses of Station Blackout Sequence) | NTHU NDLTD | 碩 | 無口試日期 |
嚴重事故分析(Severe Accident Analysis)、電廠全黑(station blackout)、氫氣(hydrogen production)、放射性物質外釋(radionuclides releases)、輻射源項(undefined) 嚴重事故分... | ||||
| 102 | 核三廠 M... 核三廠 MELCOR 程式輸入檔的建立與電廠全黑嚴重事故分析 (Building MELCOR Input Deck of Maanshan Nuclear Power Station and Analyses of Station Blackout Sequence) | NTHU NDLTD | 碩 | 無口試日期 |
嚴重事故分析、氫氣產生量、輻射源項分析 嚴重事故分... | ||||
| 102 | 使用MEL... 使用MELCOR程式模擬福島一廠三號機事故與放射性物質外釋量之分析 (Analysis of Unit 3 Fukushima Nuclear Power Plant Accident Using MELCOR 1.8.5 Code) | NTHU NDLTD | 碩 | 無口試日期 |
核電廠嚴重事故分析(Severe Accident Analysis)、福島一廠事故分析(Fukushima Accident)、氫氣燃燒(Hydrogen Burn) 核電廠嚴重... | ||||
| 102 | 核二廠ME... 核二廠MELCOR程式輸入檔的建立與電廠全黑嚴重事故分析 (Building MELCOR Input Deck of Kuosheng Nuclear Power Station and Analyses of Station Blackout Sequence) | NTHU NDLTD | 碩 | 無口試日期 |
MELCOR(Source Terms)、MAAP5(Severe Accident Analysis)、嚴重事故分析(undefined)、輻射源項(undefined) MELCO... | ||||
| 101 | 核一廠斷然... 核一廠斷然處置措施之安全度評估 (A Probabilistic Safety Assessment of Ultimate Response Guidelines of Chinshan Nuclear Power Plant) | NTHU NDLTD | 碩 | 無口試日期 |
核一廠、斷然處置措施、安全度評估 核一廠、斷... | ||||
| 101 | 核三廠斷然... 核三廠斷然處置措施對一階安全度評估量化之結果影響 (A Probabilistics Safety Assessment of Ultimate Response Guidelines of Maanshan Nuclear Power Plant) | NTHU NDLTD | 碩 | 無口試日期 |
斷然處置措施、核三廠、電廠全黑、安全度評估 斷然處置措... | ||||
| 101 | 核二廠斷然... 核二廠斷然處置措施之安全度評估 (A Probabilistic Safety Assessment of Ultimate Response Guidelines of Kuosheng Nuclear Power Plant) | NTHU NDLTD | 碩 | 無口試日期 |
核二廠(Kuosheng nuclear power plants)、機組斷然程序指引(Ultimate Response Guidelines)、安全度評估(Probabilistic Safety Assessment)、爐心熔損頻率(Core Damage Frequency) 核二廠(K... |