Burnup
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- 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