CR-39... 固態核軌跡底片應用於航空高度下宇宙輻射量測的可行性研究 (Feasibility Study of Cosmic Radiation Measurements at Aviation Altitudes by CR-39 PNTD)more

CR-39 固態核軌跡底片應用於航空高度下宇宙輻射量測的可行性研究 (Feasibility Study of Cosmic Radiation Measurements at Aviation Altitudes by CR-39 PNTD)

簡化模型預... 估肺部腫瘤劑量在硼中子捕獲治療的發展與應用 (Development and Application of a Simplified Model for the Estimation of Lung Tumor Dose in BNCT)more

簡化模型預估肺部腫瘤劑量在硼中子捕獲治療的發展與應用 (Development and Application of a Simplified Model for the Estimation of Lung Tumor Dose in BNCT)

解析式構建... 展開布拉格峰方法的分析與參數選取的研究 (Parametric studies on various methodologies for creating spread-out Bragg peaks in proton therapy)more

解析式構建展開布拉格峰方法的分析與參數選取的研究 (Parametric studies on various methodologies for creating spread-out Bragg peaks in proton therapy)

硼中子捕獲... 劑量評估與治療效益的精進研究 (Improving Dose Assessment and Therapeutic Benefit of Boron Neutron Capture Therapy)more

硼中子捕獲劑量評估與治療效益的精進研究 (Improving Dose Assessment and Therapeutic Benefit of Boron Neutron Capture Therapy)

利用Tal... ys 分析70MeV 迴旋加速器產製 Tl-201、I-123、Sr-82、Ac-225、Cu-67 和Sn-117m 的可行途徑 (Analysis of Tl-201, I-123, Sr-82, Ac-225, Cu-67 and Sn-117m Possible Production Routes at a 70MeV Cyclotron by Talys)more

利用Talys 分析70MeV 迴旋加速器產製 Tl-201、I-123、Sr-82、Ac-225、Cu-67 和Sn-117m 的可行途徑 (Analysis of Tl-201, I-123, Sr-82, Ac-225, Cu-67 and Sn-117m Possible Production Routes at a 70MeV Cyclotron by Talys)

THOR-... BNCT治療室停止照射後殘存劑量率的變化 (Residual dose rates in the THOR-BNCT treatment room)more

THOR-BNCT治療室停止照射後殘存劑量率的變化 (Residual dose rates in the THOR-BNCT treatment room)

異質頭型假... 體開發與硼中子捕獲治療計畫驗證 (Development of a Heterogeneous Phantom and Validation of Boron Neutron Capture Therapy Treatment Planning System)more

異質頭型假體開發與硼中子捕獲治療計畫驗證 (Development of a Heterogeneous Phantom and Validation of Boron Neutron Capture Therapy Treatment Planning System)

台灣參考人... 假體的光子與中子通量劑量轉換係數 (Fluence-to-Dose Conversion Coefficients of Photons and Neutrons with Taiwanese Reference Phantoms)more

台灣參考人假體的光子與中子通量劑量轉換係數 (Fluence-to-Dose Conversion Coefficients of Photons and Neutrons with Taiwanese Reference Phantoms)

用過核子燃... 料輻射源與衰變熱的分析 : 燃耗計算、內插近似與機器學習法的比較 (Source Term and Decay Heat of Spent Nuclear Fuels: Comparison of Depletion Calculations, Database Interpolation, and Machine Learning Methods)more

用過核子燃料輻射源與衰變熱的分析 : 燃耗計算、內插近似與機器學習法的比較 (Source Term and Decay Heat of Spent Nuclear Fuels: Comparison of Depletion Calculations, Database Interpolation, and Machine Learning Methods)

鎦-177... 胜肽受體放射性核種治療的體內劑量與體外曝露之評估 (Evaluation of the internal dosimetry and external exposure in 177Lu-DOTATATE peptide receptor radionuclide therapy)more

鎦-177胜肽受體放射性核種治療的體內劑量與體外曝露之評估 (Evaluation of the internal dosimetry and external exposure in 177Lu-DOTATATE peptide receptor radionuclide therapy)

晶格隨機漫... 步模型與蒙地卡羅粒子遷移模擬 (Lattice Random Walk Modeling and Monte Carlo Particle Transport Simulation)more

晶格隨機漫步模型與蒙地卡羅粒子遷移模擬 (Lattice Random Walk Modeling and Monte Carlo Particle Transport Simulation)

混合式輻射... 遷移計算應用於用過核子燃料乾式貯存屏蔽分析的研究 (Studies on Hybrid Deterministic/Monte Carlo Calculations in Shielding Analysis of Spent Nuclear Fuel Dry Storage)more

混合式輻射遷移計算應用於用過核子燃料乾式貯存屏蔽分析的研究 (Studies on Hybrid Deterministic/Monte Carlo Calculations in Shielding Analysis of Spent Nuclear Fuel Dry Storage)

整合式活化... 裝置用於清大硼中子捕獲治療射束中子能譜確認之理論與實驗測試 (A theoretical and experimental test on the performance of an integrated activation device for neutron spectrum confirmation at THOR-BNCT)more

整合式活化裝置用於清大硼中子捕獲治療射束中子能譜確認之理論與實驗測試 (A theoretical and experimental test on the performance of an integrated activation device for neutron spectrum confirmation at THOR-BNCT)

核醫藥物與... 透視攝影作業操作人員的劑量評估：手部/眼球水晶體等價劑量與全身有效劑量的關係 (Dose assessment for workers during nuclear medicine and fluoroscopy procedures: relation between hand/eye lens equivalent doses and whole-body effective dose)more

核醫藥物與透視攝影作業操作人員的劑量評估：手部/眼球水晶體等價劑量與全身有效劑量的關係 (Dose assessment for workers during nuclear medicine and fluoroscopy procedures: relation between hand/eye lens equivalent doses and whole-body effective dose)

台灣迴旋加... 速器醫用同位素產製設施之伴隨中子產率與物質活化潛勢的比較分析 (A comparative study on the prediction of neutron yields and associated activation of materials for cyclotron-based medical isotope production facilities in Taiwan)more

台灣迴旋加速器醫用同位素產製設施之伴隨中子產率與物質活化潛勢的比較分析 (A comparative study on the prediction of neutron yields and associated activation of materials for cyclotron-based medical isotope production facilities in Taiwan)

靜態隨機存... 取記憶體的飛航輻射單粒子翻轉效應評估：以台灣重要國際航線為例 (Single Event Upset Assessment for Static Random-Access Memory Onboard the Aircraft in Popular Flight Routes from Taiwan)more

靜態隨機存取記憶體的飛航輻射單粒子翻轉效應評估：以台灣重要國際航線為例 (Single Event Upset Assessment for Static Random-Access Memory Onboard the Aircraft in Popular Flight Routes from Taiwan)

飛機結構對... 於人員飛航劑量評估的影響分析 (Analysis of the Influence of Aircraft Structure on the Evaluation of the Doses to Aircrew Members)more

飛機結構對於人員飛航劑量評估的影響分析 (Analysis of the Influence of Aircraft Structure on the Evaluation of the Doses to Aircrew Members)

PIMAL... 擬人假體用於通量劑量轉換係數計算的研究 (Studies on the Calculation of Fluence to Effective Dose Conversion Coefficients with PIMAL Stylized Phantom)more

PIMAL擬人假體用於通量劑量轉換係數計算的研究 (Studies on the Calculation of Fluence to Effective Dose Conversion Coefficients with PIMAL Stylized Phantom)

整合式中子... 能譜確認裝置用於THOR BNCT的射束特性與中子能譜測量 (Development and Test of an Integrated Device for Spectrum Confirmation at THOR-BNCT)more

整合式中子能譜確認裝置用於THOR BNCT的射束特性與中子能譜測量 (Development and Test of an Integrated Device for Spectrum Confirmation at THOR-BNCT)

新版宇宙射... 線飛航劑量評估程式的開發與應用 (Development and Applications of the New NTHU Flight Dose Calculator)more

新版宇宙射線飛航劑量評估程式的開發與應用 (Development and Applications of the New NTHU Flight Dose Calculator)

延伸能量之... 中子偵檢器用於高能電子加速器輻射場的探討 (Study on extended-range neutron detectors used at high-energy electron accelerators)more

延伸能量之中子偵檢器用於高能電子加速器輻射場的探討 (Study on extended-range neutron detectors used at high-energy electron accelerators)

NCRP-... 151報告和PHITS蒙地卡羅法應用於直線加速器治療室屏蔽分析之研究 (Shielding Evaluation for Linac Radiotherapy Facilities by NCRP-151 and PHITS Monte Carlo Calculations)more

NCRP-151報告和PHITS蒙地卡羅法應用於直線加速器治療室屏蔽分析之研究 (Shielding Evaluation for Linac Radiotherapy Facilities by NCRP-151 and PHITS Monte Carlo Calculations)

動態假體P... IMAL程式的應用探討暨輔助程式開發 (Studies on the Phantom with Moving Arms and Legs (PIMAL) in dosimetry applications)more

動態假體PIMAL程式的應用探討暨輔助程式開發 (Studies on the Phantom with Moving Arms and Legs (PIMAL) in dosimetry applications)

筆型射束掃... 描質子治療機的蒙地卡羅射源模型 (Monte Carlo source models developed for pencil beam scanning proton machine)more

筆型射束掃描質子治療機的蒙地卡羅射源模型 (Monte Carlo source models developed for pencil beam scanning proton machine)

質子、重粒... 子與加速器硼中子捕獲治療設施的輻射場特性與屏蔽研究 (Radiation Field Characterization and Shielding Studies on Proton, Carbon-ion, and Accelerator-Based Boron Neutron Capture Therapy Facilities)more

質子、重粒子與加速器硼中子捕獲治療設施的輻射場特性與屏蔽研究 (Radiation Field Characterization and Shielding Studies on Proton, Carbon-ion, and Accelerator-Based Boron Neutron Capture Therapy Facilities)

質子治療誘... 發二次癌症風險評估模組之開發：考量小兒腦瘤治療之照野內外的器官 (Developing the radiation-induced second cancer risk estimation module in proton therapy: considering the organs inside and outside radiation fields in treatment of pediatric brain tumors)more

質子治療誘發二次癌症風險評估模組之開發：考量小兒腦瘤治療之照野內外的器官 (Developing the radiation-induced second cancer risk estimation module in proton therapy: considering the organs inside and outside radiation fields in treatment of pediatric brain tumors)

熔鹽式反應... 系統的計算流體力學與中子物理耦合分析 (Computational Fluid Dynamics Analyses of Molten Salt Systems with Neutronics Feedback)more

熔鹽式反應系統的計算流體力學與中子物理耦合分析 (Computational Fluid Dynamics Analyses of Molten Salt Systems with Neutronics Feedback)

不確定度量... 化分析的代理人模型 及其在核工的應用 (Robust Surrogate Models for Uncertainty Quantification and Nuclear Engineering Applications)more

不確定度量化分析的代理人模型 及其在核工的應用 (Robust Surrogate Models for Uncertainty Quantification and Nuclear Engineering Applications)

建築物內宇... 宙射線牟子與中子的研究 (Studies of cosmic-ray muons and neutrons in a concrete building)more

建築物內宇宙射線牟子與中子的研究 (Studies of cosmic-ray muons and neutrons in a concrete building)

不同燃料循... 環在資源利用與次要錒系元素減量的探討 (Theoretical Investigation on Resource Utilization and Minor Actinides Reduction in Various Fuel Cycles)more

不同燃料循環在資源利用與次要錒系元素減量的探討 (Theoretical Investigation on Resource Utilization and Minor Actinides Reduction in Various Fuel Cycles)

傳統緩速型... 中子劑量計用於高能中子輻射場的劑量低估及修正研究 (Dose Underestimation and Correction Factors for Conventional Moderated-type Neutron Dose Meters Used in High-Energy Neutron Environments)more

傳統緩速型中子劑量計用於高能中子輻射場的劑量低估及修正研究 (Dose Underestimation and Correction Factors for Conventional Moderated-type Neutron Dose Meters Used in High-Energy Neutron Environments)

台灣飛航輻... 射劑量的研究與評估程式的開發 (DEVELOPMENT, VALIDATION, AND DEMONSTRATION OF THE NTHU FLIGHT DOSE CALCULATOR)more

台灣飛航輻射劑量的研究與評估程式的開發 (DEVELOPMENT, VALIDATION, AND DEMONSTRATION OF THE NTHU FLIGHT DOSE CALCULATOR)

傳統中子偵... 檢器用於高能中子輻射場的劑量低估修正研究 (Spectral Correction Factors for Conventional Neutron Dosemeters Used in High-energy Neutron Environments – A Complete Survey of All Neutron Spectra in IAEA-TRS-403)more

傳統中子偵檢器用於高能中子輻射場的劑量低估修正研究 (Spectral Correction Factors for Conventional Neutron Dosemeters Used in High-energy Neutron Environments – A Complete Survey of All Neutron Spectra in IAEA-TRS-403)

利用OLI... NDA/EXM及MCNPX進行錸-188微脂體藥物之診療患者體內劑量評估 (Internal Dose Assessment of 188Re-Liposome Patient Estimated by OLINDA/EXM and MCNPX)more

利用OLINDA/EXM及MCNPX進行錸-188微脂體藥物之診療患者體內劑量評估 (Internal Dose Assessment of 188Re-Liposome Patient Estimated by OLINDA/EXM and MCNPX)

三維簡易自... 然對流熔鹽式反應器中子及熱水流耦合計算分析 (3D Coupled Neutronics/Thermal-Hydraulics Analyses for a Simple Natural Convection Molten Salt Reactor)more

三維簡易自然對流熔鹽式反應器中子及熱水流耦合計算分析 (3D Coupled Neutronics/Thermal-Hydraulics Analyses for a Simple Natural Convection Molten Salt Reactor)

TRITO... N/GenPMAXS/PARCS 計算序列應用於單純UOX與混合MOX燃料的簡易爐心模型 (Neutronic Simulations for Simple Core Models using TRITON/GenPMAXS/PARCS Sequence)more

TRITON/GenPMAXS/PARCS 計算序列應用於單純UOX與混合MOX燃料的簡易爐心模型 (Neutronic Simulations for Simple Core Models using TRITON/GenPMAXS/PARCS Sequence)

黃銅塊被質... 子活化的工作人員劑量與放射性廢棄物外釋之探討 (Occupational dose and radioactive waste release with activated brass aperture by proton beam)more

黃銅塊被質子活化的工作人員劑量與放射性廢棄物外釋之探討 (Occupational dose and radioactive waste release with activated brass aperture by proton beam)

簡化型蒙地... 卡羅射源模型 應用於筆型射束掃描質子治療之劑量計算研究 (A Simplified Monte Carlo Source Model used in Dose Calculation for Proton Pencil-beam Scanning)more

簡化型蒙地卡羅射源模型 應用於筆型射束掃描質子治療之劑量計算研究 (A Simplified Monte Carlo Source Model used in Dose Calculation for Proton Pencil-beam Scanning)

大氣層次級... 宇宙射線蒙地卡羅模擬及飛航劑量評估 (Monte Carlo simulations of cosmic radiation in atmosphere and an assessment of aviation dose)more

大氣層次級宇宙射線蒙地卡羅模擬及飛航劑量評估 (Monte Carlo simulations of cosmic radiation in atmosphere and an assessment of aviation dose)

球型中子活... 化偵檢器用於THOR BNCT中子能譜測量的特性與應用 (Characteristics and Application of a Spherical Type Activation-based Detector for Neutron Spectrum Measurements at the THOR BNCT Facility)more

球型中子活化偵檢器用於THOR BNCT中子能譜測量的特性與應用 (Characteristics and Application of a Spherical Type Activation-based Detector for Neutron Spectrum Measurements at the THOR BNCT Facility)

核種靈敏度... 分析用於壓水式反應器燃耗信用效應之研究 (Nuclide Sensitivity Analyses for PWR Burnup Credit Calculations)more

核種靈敏度分析用於壓水式反應器燃耗信用效應之研究 (Nuclide Sensitivity Analyses for PWR Burnup Credit Calculations)

高溫氣冷式... 反應器爐心計算的中子截面處理方法的建立與驗證研究 (The Establishment and Verification of Neutron Cross Section Processing Procedure for High Temperature Gas Cooled Reactor Core Calculation)more

高溫氣冷式反應器爐心計算的中子截面處理方法的建立與驗證研究 (The Establishment and Verification of Neutron Cross Section Processing Procedure for High Temperature Gas Cooled Reactor Core Calculation)

核一廠用過... 核子燃料乾式貯存護箱表面劑量分析與屏蔽計算模型探討 (Shielding Modeling and Surface Dose Rate Calculations for the First Spent Nuclear Fuel Dry Storage Cask in Taiwan)more

核一廠用過核子燃料乾式貯存護箱表面劑量分析與屏蔽計算模型探討 (Shielding Modeling and Surface Dose Rate Calculations for the First Spent Nuclear Fuel Dry Storage Cask in Taiwan)

加速器引發... 中子產率與物質活化之評估技術研究 (Accelerator Induced Neutron Yields and Material Activation)more

加速器引發中子產率與物質活化之評估技術研究 (Accelerator Induced Neutron Yields and Material Activation)

核醫藥物體... 內劑量計算與體外輻射防護之分析 (Analysis for Internal Dose Assessment and External Radiation Protection in Nuclear Medicine)more

核醫藥物體內劑量計算與體外輻射防護之分析 (Analysis for Internal Dose Assessment and External Radiation Protection in Nuclear Medicine)

TRITO... N/GenPMAXS/PARCS/TRACE計算平台應用於沸水式反應器爐心計算 (BWR Core Neutronic Simulations using TRITON/GenPMAXS/PARCS/TRACE Sequence)more

TRITON/GenPMAXS/PARCS/TRACE計算平台應用於沸水式反應器爐心計算 (BWR Core Neutronic Simulations using TRITON/GenPMAXS/PARCS/TRACE Sequence)

高溫研究反... 應器HTTR之爐心特性分析與計算 (Neutronics calculations and characteristic study of the HTTR high temperature test reactor core)more

高溫研究反應器HTTR之爐心特性分析與計算 (Neutronics calculations and characteristic study of the HTTR high temperature test reactor core)

六角柱型高... 溫氣冷式反應器爐心驗證計算與燃料組件計算 (Core Benchmark Calculation and Fuel Assembly Calculation for Prismatic-Type High Temperature Gas-Cooled Reactor)more

六角柱型高溫氣冷式反應器爐心驗證計算與燃料組件計算 (Core Benchmark Calculation and Fuel Assembly Calculation for Prismatic-Type High Temperature Gas-Cooled Reactor)

地心核反應... 器模型探討與燃耗計算分析 (Deep-earth Reactor Model and Burnup Analysis)more

地心核反應器模型探討與燃耗計算分析 (Deep-earth Reactor Model and Burnup Analysis)

熔鹽式反應... 器爐心物理自動化計算程序開發與應用 (An Automatic Calculation Procedure for MSR Neutronic Studies and its Applications)more

熔鹽式反應器爐心物理自動化計算程序開發與應用 (An Automatic Calculation Procedure for MSR Neutronic Studies and its Applications)