Suggested Topics within your search.
Showing 1 - 20 results of 1,064 for search '', query time: 0.07s Refine Results
  1. 1
    Technical assessment of niobium alloys data base for fusion reactor applications

    Technical assessment of niobium alloys data base for fusion reactor applications

    Published 1979
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  2. 2
    Influence of Membrane Equivalent Weight and Reinforcement on Ionic Species Crossover in All-Vanadium Redox Flow Batteries

    Influence of Membrane Equivalent Weight and Reinforcement on Ionic Species Crossover in All-Vanadium Redox Flow Batteries

    Published 2017
    Full Text (via OSTI)
    Electronic eBook
    Save to List
    Saved in:
  3. 3
    Investigation of coal structure

    Investigation of coal structure

    Published 1993
    Online Access
    Government Document Electronic eBook
    Save to List
    Saved in:
  4. 4
    Permeability changes in coal resulting from gas desorption. Eighth quarterly report, July 1, 1991--September 30, 1991

    Permeability changes in coal resulting from gas desorption. Eighth quarterly report, July 1, 1991--September 30, 1991

    Published 1991
    Online Access
    Government Document Electronic eBook
    Save to List
    Saved in:
  5. 5
    Enhancements to BISON U-Zr Metallic Fuel X447 Example Problem

    Enhancements to BISON U-Zr Metallic Fuel X447 Example Problem

    Published 2016
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  6. 6
    Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys

    Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys

    Published 2016
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  7. 7
    Selection of support structure materials for irradiation experiments in the HFIR (High Flux Isotope Reactor) at temperatures up to 500 degrees C

    Selection of support structure materials for irradiation experiments in the HFIR (High Flux Isotope Reactor) at temperatures up to 500 degrees C

    Published 1990
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  8. 8
    Demonstration of a high burnup heterogeneous core using ferritic/martensitic materials

    Demonstration of a high burnup heterogeneous core using ferritic/martensitic materials

    Published 1986
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  9. 9
    Effect of neutron irradiation on the microstructure and properties of titanium-stabilized type 316 stainless steels

    Effect of neutron irradiation on the microstructure and properties of titanium-stabilized type 316 stainless steels

    Published 1975
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  10. 10
    Irradiation performance of U-Mo monolithic fuel

    Irradiation performance of U-Mo monolithic fuel

    Published 2014
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  11. 11
    Molybdenum Disilicide Oxidation Kinetics in High Temperature Steam

    Molybdenum Disilicide Oxidation Kinetics in High Temperature Steam

    Published 2016
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  12. 12
    Rate Theory Modeling and Simulation of Silicide Fuel at LWR Conditions

    Rate Theory Modeling and Simulation of Silicide Fuel at LWR Conditions

    Published 2016
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  13. 13
    Assessment of fission-gas-induced transient swelling in metallic fuel

    Assessment of fission-gas-induced transient swelling in metallic fuel

    Published 1985
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  14. 14
    Swelling of 20% cold worked 316 stainless steel fuel pin cladding and ducts

    Swelling of 20% cold worked 316 stainless steel fuel pin cladding and ducts

    Published 1984
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  15. 15
    Postirradiation examinations of U-Pu-Zr fuel elements from subassemblies X419 and X419A

    Postirradiation examinations of U-Pu-Zr fuel elements from subassemblies X419 and X419A

    Published 1986
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  16. 16
    Dimensional changes in FFTF (Fast Flux Test Facility) austenitic cladding and ducts

    Dimensional changes in FFTF (Fast Flux Test Facility) austenitic cladding and ducts

    Published 1990
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  17. 17
    Postirradiation examination of the HT9 clad fuel test X425 at 2.9% burnup

    Postirradiation examination of the HT9 clad fuel test X425 at 2.9% burnup

    Published 1987
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  18. 18
    Metals and Ceramics Division materials science program. Annual progress report for period ending June 30, 1981

    Metals and Ceramics Division materials science program. Annual progress report for period ending June 30, 1981

    Published 1981
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  19. 19
    Studies of irradiation damage in carbons and graphites appropriate to MK II gas cooled reactors (AGRs) and to MK III gas cooled reactors (HTRs)

    Studies of irradiation damage in carbons and graphites appropriate to MK II gas cooled reactors (AGRs) and to MK III gas cooled reactors (HTRs)

    Published 1971
    Online Access (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
  20. 20
    Detailed Measurements of Local Thickness Changes for U-7Mo Dispersion Fuel Plates with Al-3.5Si Matrix After Irradiation at Different Powers in the RERTR-9B Experiment

    Detailed Measurements of Local Thickness Changes for U-7Mo Dispersion Fuel Plates with Al-3.5Si Matrix After Irradiation at Different Powers in the RERTR-9B Experiment

    Published 2017
    Full Text (via OSTI)
    Government Document Electronic eBook
    Save to List
    Saved in:
Search Tools: RSS Feed – Save Search