TAILIEUCHUNG - The Value and Impacts of Alternative Fuel Distribution Concepts- Assessing the Army’s Future Needs for Temporary Fuel Pipelines

This document describes a study done for the . Army Combined Arms Support Command (CASCOM) to assess future needs for temporary petroleum pipeline structure. At the time this work was begun, the Army was weighing further development of a new pipeline capability, the Rapidly Installed Fuel Transfer System (RIFTS), | RAND ARROYO CENTER THE ARTS CHILD POLICY CIVIL JUSTICE EDUCATION ENERGY AND ENVIRONMENT HEALTH AND HEALTH CARE INTERNATIONAL AFFAIRS NATIONAL SECURITY POPULATION AND AGING PUBLIC SAFETY SCIENCE AND TECHNOLOGY SUBSTANCE ABUSE TERRORISM AND HOMELAND SECURITY TRANSPORTATION AND INFRASTRUCTURE WORKFORCE AND WORKPLACE This PDF document was made available from as a public service of the RAND Corporation. Jump down to document 6 The RAND Corporation is a nonprofit research organization providing objective analysis and effective solutions that address the challenges facing the public and private sectors around the world. Support RAND Purchase this document Browse Books Publications Make a charitable contribution For More Information Visit RAND at Explore RAND Arroyo Center View document details Limited Electronic Distribution Rights This document and trademark s contained herein are protected by law as indicated in a notice appearing later in this work. This electronic representation of RAND intellectual property is provided for non-commercial use only. Unauthorized posting of RAND PDFs to a non-RAND Web site is prohibited. RAND PDFs are protected under copyright law. Permission is required from RAND to reproduce or reuse in another form any of our research documents for commercial use. For information on reprint and linking permissions please see RAND Permissions. This product is part of the RAND Corporation technical report series. Reports may include research findings on a specific topic that is limited in scope present discussions of the methodology employed in research provide literature reviews survey instruments modeling exercises guidelines for practitioners and research professionals and supporting documentation or deliver preliminary findings. All RAND reports undergo rigorous peer review to ensure that they meet high standards for research quality and objectivity. TECHNICAL REPORT The Value and Impacts of Alternative Fuel Distribution .

• Lịch sử - Văn hoá
• fuel
• needs
• future
• temporary
• pipelines
• army
• concepts
• impacts
• alternative
• distribution
• value
• assessing
• Large scale experiments simulating hydrogen distribution
• Spent fuel pool building during a hypothetical fuel uncovery accident scenario
• Hypothetical fuel uncovery accident scenario
• Spent Fuel Pool
• The Experiments on Spent Fuel Pool
• Different fuel assembly
• Closed fuel cycle
• Water–fuel ratio
• Nuclear energy sector
• BN 600 fuel
• Nuclear engineering and technology
• Effect of central hole on fuel temperature distribution
• Central hole on fuel temperature distribution
• Fuel average temperature
• Fuel surface temperature
• Fuel Cell
• alkaline fuel cell
• hybrids
• fuel cell system design
• Fuel Management
• Electrocatalysis
• Spectrometry analysis of fumes of mixed nuclear fuel
• Evaluation of accidental irradiation
• Living organisms by plutonium
• Radiotoxic fission product of mixed nuclear fuel
• Mixed nuclear fuel
• Fuel futures market
• Fuel price risk management
• Hedging risks
• Fuel prices in Vietnam’s market
• Fluctuations in the crude oil price
• Neutronic analysis of fuel assembly design in Small PWR
• Uranium mononitride fully ceramic micro encapsulated fuel
• SCALE and Serpent codes
• Computational design of subcritical reactor assembly with TRIGA fuel
• Characterization of a subcritical reactor assembly with TRIGA fuel
• Subcritical reactor assembly
• Different fuel configuration
• Calculate physical parameters
• The reutilization of used nuclear fuel
• PWR core without reprocessing
• Reconstruct to be reused fuel assemblies
• The used fuel pins
• Experimental simulation of activity release from leaking fuel rods
• Leaking fuel rods
• Activity release modelling
• Spent leaking fuel rods
• Scanning electron microscopy analysis of fuel matrix interaction layers
• Highlyirradiated u–mo dispersion fuel plates
• Al and al–si alloy matrices
• Fuel matrix interaction
• Focused ion beam
• Scanning electron microscopy
• Shielding analysis of dual purpose casks
• Spent nuclear fuel under normal storage conditions
• Spent nuclear fuel
• Spent fuel in storage
• Dual purpose cask
• Steady of fully ceramic microencapsulated fuel
• Transient state analyses of fully ceramic microencapsulated fuel
• Fully ceramic microencapsulated fuel
• Randomly dispersed tristructural isotropic particles via two temperature homogenized modeldi
• 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
• Mechanical analysis of the bow deformation
• Row of fuel assemblies in a PWR core
• Row of fuel assemblies
• Guide tubes and fuel rods
• Simulation of reactivity initiated accident transients
• UO2 M5® fuel rods
• ALCYONE V1
• 4 fuel performance code
• Pressurized Water ReactorPressurized Water Reactor
• Reactivity initiated Accident
• Metal fuel development
• Prototype generation iv sodium cooled fast reactor
• The prototype generation IV sodium cooled fast reactor
• Fabrication of fuel components
• Fuel verification tests
• Nuclear fuel cycle cost estimation
• Sensitivity analysis of unit costs
• The basis of an equilibrium model
• Pyro SFR fuel cycle
• The deterministic method
• Diesel distributor fuel injection pumps
• Fuel injection pumps
• Diesel distributor
• Fuel injection pumps VE
• Diesel engine exhaust emissions
• Simple fleet simulation
• PWR UOx fuel
• PWR MOx fuel
• Fuel cycle simulator CLASS
• Global sensitivity analysis
• Spent fuel management
• National spent fuel storage arrangements
• Commercial and financial arrangements
• Short term cash flow
• Fuel cycle scenario code TR_EVO
• Nuclear fuel mass
• Spanish nuclear fuel cycle
• ARCAS EU project
• TR_EVOL economic module
• systemopimization
• system processes
• Diffusion Combustion
• Deposit Accumulation
• Combustion Engines
• Fuel N Conversion
• Alternative Fuels
• Fossil Fuel Reserves