Modelling of Pellet Cladding Interaction in PWR fuel

Modelling of Pellet Cladding Interaction in PWR fuel -

CANDU Advanced Fuels and Fuel Cycles

CANDU Advanced Fuels and Fuel Cycles -

The CANDU System:A Canadian Achievement

The CANDU System:A Canadian Achievement -

Approaching the "Spent fuel standard" Without teh use of reactor

Approaching the "Spent fuel standard" Without teh use of reactor -

C I S A CCenter for International Security and Arms Control -

Compatibility Analysis on Existing Reactivity Devicesin CANDU 6 Reactors for DUPIC Fuel Cycle

Compatibility Analysis on Existing Reactivity Devicesin CANDU 6 Reactors for DUPIC Fuel Cycle -

Criticality investigations for the fixed bed nuclear reactor using thorium fuelmixed with plutonium or minor actinides

Criticality investigations for the fixed bed nuclear reactor using thorium fuelmixed with plutonium or minor actinides -

Isotopic composition and origin of uranium andplutonium in selected soil samples collected inKosovo

Isotopic composition and origin of uranium andplutonium in selected soil samples collected inKosovo -

Development of Low-Level Environmental Sampling Capabilities for Uranium at Brazilian and Argentine Laboratories by ABACC

Development of Low-Level Environmental Sampling Capabilities for Uranium at Brazilian and Argentine Laboratories by ABACC -

Isotopic analysis of uranium and plutonium using ICP-MS andestimation of burn-up of spent uranium in contaminatedenvironmental samples

Isotopic analysis of uranium and plutonium using ICP-MS andestimation of burn-up of spent uranium in contaminatedenvironmental samples{ -

SUMMARY OF DEPLETED URANIUM TEST RESULTSFOR IRAQ WAR VETERANS

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Detailed Description of Limited Recycle and Full Recycle

Detailed Description of Limited Recycle and Full Recycle -

Flexible Fuel CycleOptions for CANDU

Flexible Fuel CycleOptions for CANDU -

The Nuclear Fuel Cycle

The Nuclear Fuel Cycle -

Surface ScienceInvestigations on SpentNuclear Fuel Model Systems

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A Review of the GeochemicalProcesses Controlling the Distributionof Thorium in the Earth’s Crust andAustralia’s Thorium Resources

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Technology Development on the DUPIC Safeguards System

Technology Development on the DUPIC Safeguards System -

"Comprehensive Study of Lattice Cell Calculations for Thorium Based Fuel Cyclein Light Water Reactors Using SRAC Code

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Microspheres of UO2, ThO2 and PuO2 for theHigh Temperature Reactor

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Kinetic and thermodynamic studies of the dissolution ofthoria- urania solid solutions

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Application of INPRO Methodology to theDUPIC Fuel Cycle for the Assessment ofProliferation Resistance

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PROLIFERATION-RESISTANT TECHNOLOGY

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Thermo Physical Properties of Thoria Based Fuels

Thermo Physical Properties of Thoria Based Fuels -

The myth of proliferation-resistanttechnology

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Recent Progress on the DUPIC Fuel FabricationTechnology at KAERI

Recent Progress on the DUPIC Fuel FabricationTechnology at KAERI -

The Thorium Fuel Cycle

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SYMPOSIUM NNuclear Materials

SYMPOSIUM NNuclear Materials -

SYMPOSIUM NNuclear Materials -

UO2 Sintered Pellets Microstructure for Advanced Nuclear Fuel

UO2 Sintered Pellets Microstructure for Advanced Nuclear Fuel -

A Review of Thorium Utilization as an option for Advanced Fuel Cycle- Potential Option for Brazil in the Futu

A Review of Thorium Utilization as an option for Advanced Fuel Cycle- Potential Option for Brazil in the Futu -

Nuclear Fuels : Fabrication Processes& Technologies

Nuclear Fuels : Fabrication Processes& Technologies -

Nuclear Fuels : Property Evaluation

Nuclear Fuels : Property Evaluation -

Spent Fuel Reprocessing

Spent Fuel Reprocessing -

U-232 and the Proliferation-Resistance of U-233 in SpentFuel

U-232 and the Proliferation-Resistance of U-233 in SpentFuel -

An Example of an INPRO Assessment of an INS in the Area of WasteManagement

An Example of an INPRO Assessment of an INS in the Area of WasteManagement -

CLOSING THE NUCLEAR FUEL CYCLE

CLOSING THE NUCLEAR FUEL CYCLE -

Comparison of the burnup Characteristics";var docstoc_urltitle="Comparison of the burnup Characteristics

Comparison of the burnup Characteristics -

Analysis of Nuclear Proliferation Resistance of DUPIC Fuel Cycle

Analysis of Nuclear Proliferation Resistance of DUPIC Fuel Cycle -

Reprocessing versus Direct Disposal of Spent CANDU Nuclear Fuel:A Possible Application of Fluoride Volatility

Reprocessing versus Direct Disposal of Spent CANDU Nuclear Fuel:A Possible Application of Fluoride Volatility -

Densification Strain Rate in Sintering of ThO2 andThO2-0.25%Nb2O5 Pellets

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Behaviour of Rare Earth Elements, thorium, uranium and strontium Isotopes in SoilSamples of Bryansk Region Contaminated due to Chernobyl Accident

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Thermo-chemical Characteristics of PowderFabricated by Oxidation of Spent PWR Fuel

Thermo-chemical Characteristics of PowderFabricated by Oxidation of Spent PWR Fuel -

Technological Change of Nuclear Fuel Cycle in Korea: The case of DUPIC

Technological Change of Nuclear Fuel Cycle in Korea: The case of DUPIC -

UO2 Sintered Pellets Microstructure for Advanced Nuclear Fuel

UO2 Sintered Pellets Microstructure for Advanced Nuclear Fuel -

Constraining TRU Production in PWRs with Heterogeneous UO2 – ThO2 Assembly

Constraining TRU Production in PWRs with Heterogeneous UO2 – ThO2 Assembly -

Thorium: The PreferredNu clear Fuel of the Future

Thorium: The PreferredNuclear Fuel of the Future -

Small PWR Using Coated Particle Fuel with Ceramics Cladding

Small PWR Using Coated Particle Fuel with Ceramics Cladding -

A Review of Thorium Utilization as an option for Advanced Fuel Cycle-Potential Option for Brazil in the Future

A Review of Thorium Utilization as an option for Advanced Fuel Cycle-Potential Option for Brazil in the Future -

THORIA-BASED CERMET NUCLEAR FUEL: CERMET FABRICATION ANDBEHAVIOR ESTIMATES

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Manufacturing Technology for Thorium Based Fuel Elements

Manufacturing Technology for Thorium Based Fuel Elements -

Manufacturing Technology for Thorium Based Fuel Elements -

CANDU FUEL-CYCLE VISION

CANDU FUEL-CYCLE VISION -

Reactor ProgrammeResearch Reactors

Reactor ProgrammeResearch Reactors -

Saudi Arabian Nuclear Science Bibliography: Open Literature Citations

Saudi Arabian Nuclear Science Bibliography: Open Literature Citations -

CANDU Advanced Fuels and Fuel Cycles

CANDU Advanced Fuels and Fuel Cycles -

"CANDU Advanced Fuels and Fuel Cycles

CANDU Advanced Fuels and Fuel Cycles -

A New Technique Provides Faster Particle Size Analysis at a LowerCost Compared to Conventional Methods

A New Technique Provides Faster Particle Size Analysis at a LowerCost Compared to Conventional Methods -

Investigations on enhanced nuclear fuelutilization in light water reactors by mixing ofuranium and thorium based heavy metals

Investigations on enhanced nuclear fuelutilization in light water reactors by mixing ofuranium and thorium based heavy metals -

"Criticality investigations for the fixed bed nuclear reactor using thorium fuelmixed with plutonium or minor actinides

Criticality investigations for the fixed bed nuclear reactor using thorium fuelmixed with plutonium or minor actinides -

urvey and Exposure Estimates of Uranium in Desert Lettuce

Survey and Exposure Estimates of Uranium in Desert Lettuce -

Canadian Soil Quality Guidelines for Uranium:Environmental and Human Health

Canadian Soil Quality Guidelines for Uranium:Environmental and Human Health -

Automated Determination of PPQ Levelsof Thorium in High Purity CopperUsing the ESI TRUFAST System and ICPMS Detection

Automated Determination of PPQ Levelsof Thorium in High Purity CopperUsing the ESI TRUFAST System and ICPMS Detection -

This document was prepared in conjunction with work accomplished underContract No. DE-AC09-08SR22470 with the U.S. Department of Energy

This document was prepared in conjunction with work accomplished underContract No. DE-AC09-08SR22470 with the U.S. Department of Energy. -

Assessment of DUPIC Fuel Cycle using IAEA INPRO Methodology

Assessment of DUPIC Fuel Cycle using IAEA INPRO Methodology -

Thermo-chemical Characteristics of PowderFabricated by Oxidation of Spent PWR Fuel

Thermo-chemical Characteristics of PowderFabricated by Oxidation of Spent PWR Fuel -

INTERNATIONAL MEETINGON LWR FUEL PERFORMANCE“NUCLEAR FUEL: ADDRESSING THE FUTURE

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Canadian Soil Quality Guidelines for Uranium:Environmental and Human Health

Canadian Soil Quality Guidelines for Uranium:Environmental and Human Health -

CANDU FUEL-CYCLE VISION

CANDU FUEL-CYCLE VISION -

Reactor ProgrammeResearch Reactors

Reactor ProgrammeResearch Reactors -

Saudi Arabian Nuclear Science Bibliography: Open Literature Citations

Saudi Arabian Nuclear Science Bibliography: Open Literature Citations -

CANDU Advanced Fuels and Fuel Cycles

CANDU Advanced Fuels and Fuel Cycles -

A New Technique Provides Faster Particle Size Analysis at a LowerCost Compared to Conventional Methods

A New Technique Provides Faster Particle Size Analysis at a LowerCost Compared to Conventional Methods -

Investigations on enhanced nuclear fuelutilization in light water reactors by mixing ofuranium and thorium based heavy metals

Investigations on enhanced nuclear fuelutilization in light water reactors by mixing ofuranium and thorium based heavy metals -

Criticality investigations for the fixed bed nuclear reactor using thorium fuelmixed with plutonium or minor actinides

Criticality investigations for the fixed bed nuclear reactor using thorium fuelmixed with plutonium or minor actinides -

Survey and Exposure Estimates of Uranium in Desert Lettuce

Survey and Exposure Estimates of Uranium in Desert Lettuce -

THE DEVELOPMENT AND APPLICATION OF SCDAP-3D©

THE DEVELOPMENT AND APPLICATION OF SCDAP-3D© -

Thorium Fuel Performance in a Tight Pitch LWR Lattice

Thorium Fuel Performance in a Tight Pitch LWR Lattice -

ON THE USE OF THORIUM INLIGHT WATER REACTORS

ON THE USE OF THORIUM INLIGHT WATER REACTORS -

CLOSING THE NUCLEAR FUEL CYCLE

CLOSING THE NUCLEAR FUEL CYCLE -

THORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDUPOWER REACTOR

THORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDUPOWER REACTOR -

Constraining TRU Production in PWRs with Heterogeneous UO2 – ThO2 Assembly

Constraining TRU Production in PWRs with Heterogeneous UO2 – ThO2 Assembly -

Thorium: The Preferred Nuclear Fuel of the Future

Thorium: The PreferredNuclear Fuel of the Future -

APPLICATION OF CLOSE-RANGE PHOTOGRAMMETRY AND DIGITALPHOTOGRAPHY ANALYSIS FOR THE ESTIMATION OF LEAF AREA INDEX IN AGREENHOUSE TOMATO CULTURE -

An Inexpensive, Accurate Method for Measuring Leaf Area andDefoliation Through Digital Image Analysis

An Inexpensive, Accurate Method for Measuring Leaf Area andDefoliation Through Digital Image Analysis -

Small PWR Using Coated Particle Fuel with Ceramics Cladding

Small PWR Using Coated Particle Fuel with Ceramics Cladding -

A Review of Thorium Utilization as an option for Advanced Fuel Cycle-Potential Option for Brazil in the Future

A Review of Thorium Utilization as an option for Advanced Fuel Cycle-Potential Option for Brazil in the Future -

THORIA-BASED CERMET NUCLEAR FUEL: CERMET FABRICATION ANDBEHAVIOR ESTIMATES

THORIA-BASED CERMET NUCLEAR FUEL: CERMET FABRICATION ANDBEHAVIOR ESTIMATES -

Manufacturing Technology for Thorium Based Fuel Elements

Manufacturing Technology for Thorium Based Fuel Elements -

Fabrication and Termal properties

Fabrication and Termal properties -

Indoor Residual Spraying (IRS) for Malaria Control Indefinite Quantity Contract (IQC) Task Order 1 (TO1)

Indoor Residual Spraying (IRS) for Malaria Control Indefinite Quantity Contract (IQC) Task Order 1 (TO1) -

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Carbon Based Material Applications in High temperature Nucler Reactors

Carbon Based Material Applications in High temperature Nucler Reactors -

XAFS study of local structure with picometer accuracy:Th1-xUxO2 and Th1-xPuxO2 solid solutions

XAFS study of local structure with picometer accuracy:Th1-xUxO2 and Th1-xPuxO2 solid solutions -

Comprehensive Study of Lattice Cell Calculations for Thorium Based Fuel Cyclein Light Water Reactors Using SRAC Code

Comprehensive Study of Lattice Cell Calculations for Thorium Based Fuel Cyclein Light Water Reactors Using SRAC Code -

INVESTIGATIONS OF THORIUM BASED FUEL TO IMPROVEACTINIDE BURNING RATE IN S-PRISM REACTOR

INVESTIGATIONS OF THORIUM BASED FUEL TO IMPROVEACTINIDE BURNING RATE IN S-PRISM REACTOR -

Operation of CANDU power reactor in thoriumself-su±cient fuel cycle

Operation of CANDU power reactor in thoriumself-su±cient fuel cycle -

Fissile and Fusile Breeding in the Thorium Fusion Fission Hybrid

Fissile and Fusile Breeding in the Thorium Fusion Fission Hybrid -

A Review of Thorium Utilization as an option for Advanced Fuel Cycle- Potential Option for Brazil in the Future

A Review of Thorium Utilization as an option for Advanced Fuel Cycle- Potential Option for Brazil in the Future -

Modular Helium Reactor (MHR) for Oil SandsExtraction

Modular Helium Reactor (MHR) for Oil SandsExtraction -

Estimating and Mapping Impervious Surface Area by RegressionAnalysis of Landsat Imagery -