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Burnup
Ml19149a371
Vver and Rbmk Cross Section Libraries for Origen-Arp
The Effect of Burnup and Separation Efficiency on Uranium Utilization and Radiotoxicity
Nuclear Fuel Cycles Technology Assessment
The Burnup Dependence of Light Water Reactor Spent Fuel Oxidation
Nuclear Reactors and Plutonium Production
Fuel Burnup and Enrichment Extension Preparation Strategy
Burnup Determinaton of Nuclear Fuel
Burnup Credit Criticality Safety Analysis Using STARBUCS
Reactor Fuel Isotopics and Code Validation for Nuclear Applications
Performance Assessment of Spent Fuel Assemblies Removed from Shutdown Rbmk-1000 Power Units for Reburning in Operating Power Units
Advances by the Integral Fast Reactor Program De91 011174
HTR-N Plutonium Cell Burnup Benchmark: Definition, Results & Intercomparison
A Phased Development of Breed-And-Burn Reactors for Enhanced Nuclear Energy Sustainability
The Plutonium Breeder Thomas B
Tschernobyl-Katastrophe"
Impact of Extended Burnup on the Nuclear Fuel Cycle
Plutonium Oxide Water Reactor Fuel on Spent Fuel Management No
Top View
NUREG/CR-6998, Review of Information for Spent Nuclear Fuel
Maximum Fuel Utilization in Advanced Fast Reactors Without Actinides Separation
EXPERIMENTAL and THEORETICAL DETERMINATION of BURNUP and HEAVY ISOTOPE CONTENT in a FUEL ASSEMBLY «Ff IRRADIATED in the GARIGLIANO BOILING WATER REACTOR
Reactor-Grade and Weapons-Grade Plutonium in Nuclear Explosives
Rbmk Fuel Assemblies: Current Status and Perspectives
Design Choices and Severe Accident Possibilities in India’S Prototype Fast Breeder Reactor
Back-End of the Fuel Cycle in a 1000 Cwe Nuclear Scenario
Burnup Credit Evaluation for BWR Spent Fuel from Full Core Calculations
L%%Losalamos Scientific Laboratory
The Set of New Libraries of Origen2 Code Based on Jendl-3.2
Multilateralization of the Nuclear Fuel Cycle: Assessing Existing Proposals
The Integral Fast Reactor*
FY11 Summary Report Augmentation of International Spent Fuel Database
The Fission Properties of Curium Separated from Spent Nuclear Fuel
Technical and Economic Limits to Fuel Burnup Extension Proceedings of a Technical Committee Meeting Held in San Carlos De Bariloche, Argentina, 15–19 November 1999
Comparison of Burnup Credit Uncertainty Quantification Methods
The Use of Curium Neutrons to Verify Plutonium in Spent Fuel and Reprocessing Wastes
Assessment of the Radiotoxicity of Spent Nuclear Fuel from a Fleet of PWR Reactors
Fuel Performance Modeling of High Burnup Mixed Oxide Fuel for Hard Spectrum Lwrs
Heat from Reactor-Grade Plutonium: an Outdated Worry
Characterization and Modeling of High Burn-Up Mixed Oxide Fuel
Analysis METHODOLOGY for RBMK-1500 CORE Safety AND
Feasibility Study of Thorium-Plutonium Mixed Oxide
Proliferation Relevance and Safeguards Implications of Partitioning and Transmutation Nuclear Fuel Cycles
Determination of Neutron Emission from Spent Fuel for Safeguards Verification
R&T Report No
Fuel Performance Considerations and Data Needs for Burnup Above 62 Gwd/MTU In-Reactor Performance, Storage, and Transportation of Spent Nuclear Fuel
Reactor-Grade Plutonium and Nuclear Weapons: Exploding the Myths REACTOR- GRADE PLUTONIUM and NUCLEAR WEAPONS
The Integral Fast Reactor Concept*
Impact of Extended Burnup on the Nuclear Fuel Cycle