tailieunhanh - An integrated multicriteria decision making approach for evaluating nuclear fuel cycle systems for long term sustainability on the basis of an equilibrium model: Technique for order of preference by similarity to ideal solution, preference ranking organization method for enrichment evaluation, and multiattribute utility theory combined with analytic hierarchy process

The focus on the issues surrounding spent nuclear fuel and lifetime extension of old nuclear power plants continues to grow nowadays. A transparent decision-making process to identify the best suitable nuclear fuel cycle (NFC) is considered to be the key task in the current situation. | An integrated multicriteria decision making approach for evaluating nuclear fuel cycle systems for long term sustainability on the basis of an equilibrium model: Technique for order of preference by similarity to ideal solution, preference ranking organization method for enrichment evaluation, and multiattribute utility theory combined with analytic hierarchy process N u c l e a r E n g i n e e r i n g a n d T e c h n o l o g y 4 9 ( 2 0 1 7 ) 1 4 8 e1 6 4 Available online at ScienceDirect Nuclear Engineering and Technology journal homepage: Original Article An Integrated Multicriteria Decision-Making Approach for Evaluating Nuclear Fuel Cycle Systems for Long-term Sustainability on the Basis of an Equilibrium Model: Technique for Order of Preference by Similarity to Ideal Solution, Preference Ranking Organization Method for Enrichment Evaluation, and Multiattribute Utility Theory Combined with Analytic Hierarchy Process Saerom Yoon a,*, Sungyeol Choi b, and Wonil Ko c a Department of Quantum Energy Chemical Engineering, Korea University of Science and Technology (KUST), Gajungro 217, Yuseong-Gu, Daejeon 305-350, Republic of Korea b Ulsan National Institute of Science and Technology, UNIST-Gil 50, Eonyang-eup, Ulju-Gun 689-798, Republic of Korea c Nonproliferation System Development Division, Korea Atomic Energy Research Institute (KAERI), Daedeok-Daero 989-111, Yuseong-Gu, Daejeon 305-353, Republic of Korea article info abstract Article history: The focus on the issues surrounding spent nuclear fuel and lifetime extension of old nu- Received 29 July 2015 clear power plants continues to grow nowadays. A transparent decision-making process to Received in revised form identify the best suitable nuclear fuel cycle (NFC) is considered to be the key task in the 7 July 2016 current situation. Through this study, an attempt is made to develop an equilibrium model Accepted 8 July 2016 .

• Kỹ Thuật - Công Nghệ
• Nuclear engineering and technology
• An integrated multicriteria decision making approach
• Evaluating nuclear fuel cycle systems
• Long term sustainability on the basis of an equilibrium model
• Technique for order of preference by similarity to ideal solution
• preference ranking organization method for enrichment evaluation
• Multiattribute utility theory combined with analytic hierarchy process
• Integral nuclear data validation
• Experimental spent nuclear fuel compositions
• Economic Co operation and Development
• Nuclear Energy Agency
• Nuclear Criticality Safety
• Expanded spent fuel isotopic compositions
• Nuclear reactor vessel water level prediction during severe accidents
• Deep neural networks
• Nuclear power plants
• Maintain nuclear reactor integrity
• Special issue on the International Symposium
• Future Instrumentation and Control for Nuclear Power Plants
• The Nuclear Engineering and Technolog
• Parameter identifiability of Boolean networks
• Application to fault diagnosis of nuclear plants
• Fault diagnosis of nuclear plants
• Nuclear Heating Reactor
• Sensor selection strategy
• Radioactive effluents released from Korean nuclear power plants
• The resulting radiation doses to members of the public
• Korean nuclear power plants
• Nuclear power plant
• The recycling of nuclear graphite after micro oxidation
• Nuclear graphite after micro oxidation
• Whether ground micro oxidation graphite
• The oxidized graphite particles
• The recycling of nuclear graphite
• Statistical model for forecasting uranium prices
• Estimate the nuclear fuel cycle cost
• Nuclear Fuel Cycle Cost
• Nuclear fuel cycle cost calculation
• The statistical autoregressive integrated moving average
• Distinct properties of tungsten austenitic stainless alloy
• Potential nuclear engineering material
• Interchanging the molybdenum in standard SS316 by tungsten
• Gamma and neutron shielding Interchanging the molybdenum
• Nuclear engineering and design
• Brayton cycle
• Supercritical carbon dioxide
• Nuclear engineering
• Safety analysis
• Control strategy
• Seismic fragility evaluation
• The base isolated nuclear power plant piping system
• The failure criterion based on stress strain
• Nuclear power plant piping system
• Seismic fragility analysis
• BNL NRC benchmark model
• Feasibility study on photo production
• 99mTc with the nuclear resonance fluorescence
• The nuclear resonance fluorescence
• High intensity laser Compton scattering
• Improved PCA method
• Sensor fault detection and isolation in a nuclear power plant
• Sensor fault detection and isolation
• Influences of heating processes on properties
• Microstructure of porous CeO2 beads
• Surrogate for nuclear fuels fabricated
• Microfluidic sol gel process
• The ceramic nuclear fuel particles
• Sensitivity analysis of thermal hydraulic parameters
• The corrosion intensity in nuclear power plant steam generators
• Nuclear power plant steam generators
• The failure of steam generators
• The heat exchangers
• Architectural model driven dependability analysis
• Computer based safety system in nuclear power plant
• Safety system in nuclear power plant
• Embedded Real Time Safety Systems
• Mitigation of high energy arcing faults
• Nuclear power plant medium voltage switchgear
• High energy arcing fault
• Ultra high performance fiber reinforced concrete nuclear waste container
• High level waste
• Ultra high performance fiber reinforced concrete material
• The dry storage container
• Canadian Nuclear facilities
• Real time estimation of break sizes during LOCA
• Nuclear power plants using NARX neural network
• Nonlinear autoregressive with exogenous inputs
• Loss of coolant accidents
• Nordic research and development cooperation
• Strengthen nuclear reactor safety after the Fukushima accident
• The Fukushima accident
• Nordic Nuclear Safety Research
• Seismic response characteristics
• Isolated AP1000 nuclear shield building subjected
• Beyond design basis earthquake shaking
• Beyond Design Basis Earthquake
• Nuclear Shield Building
• Uncertainty analysis of containment dose rate
• Containment dose rate for core damage assessment
• Containment Radiation Monitor
• Core Damage Assessment
• An evaluation method for nuclear fuel debrisefiltering performance
• Nuclear fuel debrisefiltering performance
• Comprehensive Debris Filtering Efficiency
• Debris Filtering Performance
• Debris Induced Failure
• Development of earthquake instrumentation for shutdown
• Restart criteria of the nuclear power plant
• Multivariable decision making process
• The nuclear power plant
• Development of an information reference system
• Reconstruction models of nuclear power plants
• Work site reconstruction models
• Six nuclear power plant workers
• Nondestructive inspection of spent nuclear fuel storage canisters
• Shear horizontal guided waves
• Spent nuclear fuel storage canisters
• The cask protecting the canister
• Geometric constrains inside