DOCSLIB.ORG
  • Sign Up
  • Log In
  • Upload
  • Sign Up
  • Log In
  • Upload
  • Home
  • »  Tags
  • »  Decay heat

Decay heat

  • CURRENT STATUS of DECAY HEAT MEASUREMENTS, EVALUATIONS, and NEEDS*

    CURRENT STATUS of DECAY HEAT MEASUREMENTS, EVALUATIONS, and NEEDS*

  • Chapter 4 — Fuel Cycles

    Chapter 4 — Fuel Cycles

  • Doe Nuclear Physics Reactor Theory Handbook

    Doe Nuclear Physics Reactor Theory Handbook

  • Effects of Heat from High-Level Waste on Performance of Deep Geological Repository Components Iaea, Vienna, 1984 Iaea-Tecdoc-319

    Effects of Heat from High-Level Waste on Performance of Deep Geological Repository Components Iaea, Vienna, 1984 Iaea-Tecdoc-319

  • Nuscale Design-Specific Review Standard Section 5.4.7, Decay Heat

    Nuscale Design-Specific Review Standard Section 5.4.7, Decay Heat

  • DOE FUNDAMENTALS HANDBOOK NUCLEAR PHYSICS and REACTOR THEORY Volume 1 of 2

    DOE FUNDAMENTALS HANDBOOK NUCLEAR PHYSICS and REACTOR THEORY Volume 1 of 2

  • The Fuel Cycle Implications of Nuclear Process Heat

    The Fuel Cycle Implications of Nuclear Process Heat

  • Optimization of Pu-238 Production in the Advanced Test Reactor

    Optimization of Pu-238 Production in the Advanced Test Reactor

  • Decay Heat Removal and Heat Transfer Under Normal and Accident Conditions in Gas Cooled Reactors

    Decay Heat Removal and Heat Transfer Under Normal and Accident Conditions in Gas Cooled Reactors

  • Fr0104396 Long-Term Behavior of Radiotoxicity and Decay Heat Power of Spent Uranium-Plutonium and Thorium Fuel

    Fr0104396 Long-Term Behavior of Radiotoxicity and Decay Heat Power of Spent Uranium-Plutonium and Thorium Fuel

  • Prospects and Challenges for a Global Expansion of Nuclear Energy

    Prospects and Challenges for a Global Expansion of Nuclear Energy

  • "A Bevlscd ANS Standard for Decay Heat from Fission Products" Invited Paper by Virgil E

  • Multi-Mission Radioisotope Thermoelectric Generator (MMRTG)

    Multi-Mission Radioisotope Thermoelectric Generator (MMRTG)

  • Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel Using Scale

    Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel Using Scale

  • Safety and Regulatory Issues of the Thorium Fuel Cycle

    Safety and Regulatory Issues of the Thorium Fuel Cycle

  • Nuclear Data Requirements for Decay Heat Calculations

    Nuclear Data Requirements for Decay Heat Calculations

  • Attachment 1, Appendix K Decay Heat Standards

    Attachment 1, Appendix K Decay Heat Standards

  • Long-Term Heat Load Calculation Methodology for Spent Nuclear Fuel

    Long-Term Heat Load Calculation Methodology for Spent Nuclear Fuel

Top View
  • Investigation of Spent Nuclear Fuel Pool Coolability
  • Neutronic Characterization and Decay Heat Calculations in the In-Vessel Fuel Storage Facilities for MYRRHA/FASTEF ⇑ S
  • Decay Heat Calculations Based on Theoretical Estimation of Average Beta- and Gamma-Energies Released from Short-Lived Fission Products
  • Nuclear Power Technologies for Deep Space and Planetary Missions
  • Decay Heat Calculations for Reactors: Development of a Computer Code ADWITA
  • Role of Decay Heat in Advanced Fuel Cycles
  • Thermal Evolution Near Heat-Generating Nuclear Waste Canisters Disposed in Horizontal Drillholes
  • Evaluation of Aqueous and Powder Processing Techniques for Production of Pu-238-Fueled General Purpose Heat Sources
  • Managing the Plutonium Surplus: Applications and Technical Options
  • ( RTG) Using COMSOL Simulation
  • Radioactive Heat Production of Six Geologically Important Nuclides
  • Thorium Fuel Cycle for a Molten Salt Reactor: State of Missouri Feasibility Study
  • Thorium Fuel Cycle — Potential Benefits and Challenges
  • Economical Production of Pu238. Steven Howe 1, Jorge Navarro1, Douglas Crawford1, Terry Ring2
  • Reducing Material Attractiveness Utilizing Pu-238 and U-232
  • Commercial Spent Nuclear Fuel
  • Heat from Reactor-Grade Plutonium: an Outdated Worry
  • Technical Report 97-13


© 2024 Docslib.org    Feedback