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  1. 1

    An alternative to the SAS2H/ORIGEN-S sequence to account for water-density effects in BWR systems

    Published 1996
    Online Access
    Government Document Electronic eBook
  2. 2

    FMDP Reactor Alternative Summary Report Volume 2 - CANDU heavy water reactor alternative.

    Published 1996
    Online Access
    Government Document Electronic eBook
  3. 3

    Third annual report high-temperature materials and reactor components development programs. Volume II. Materials.

    Published 1964
    Online Access
    Government Document Electronic eBook
  4. 4

    TOWER SHIELDING REACTOR II DESIGN AND OPERATION REPORT. VOL. 1. DESCRIPTION.

    Published 1970
    Online Access (via OSTI)
    Government Document Electronic eBook
  5. 5

    Improved specifications for fast reactor fuel by Powers, H G, Dutt, D S, Schwallie, A L

    Published 1982
    Online Access
    Government Document Electronic eBook
  6. 6

    PWR RESEARCH AND DEVELOPMENT PROGRAM. TEST REPORT. GAMMA SCANNING SPENT SM-1 CORE I FUEL ELEMENTS. TEST 318

    Published 1961
    Online Access
    Government Document Electronic eBook
  7. 7

    RADIOACTIVITY IN FFTF CLOSED LOOPS.

    Published 1967
    Online Access
    Government Document Electronic eBook
  8. 8

    Integral Fast Reactor fuel pin processor

    Published 1993
    Online Access (via OSTI)
    Government Document Electronic eBook
  9. 9

    Dissolution Flowsheet for High Flux Isotope Reactor Fuel

    Published 2016
    Online Access (via OSTI)
    Government Document Electronic eBook
  10. 10

    TITLE II FUEL ASSEMBLY HANDLING EXPERIMENT FOR THE EXPERIMENTAL GAS COOLED REACTOR

    Published 1961
    Online Access (via OSTI)
    Government Document Electronic eBook
  11. 11

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

    Published 1990
    Online Access (via OSTI)
    Government Document Electronic eBook
  12. 12

    STUDIES IN THE IMPREGNATION OF GRAPHITE WITH URANIUM

    Published 1950
    Online Access (via OSTI)
    Government Document Electronic eBook
  13. 13

    OPERATING EXPERIENCE AND DESIGN TRENDS FOR HELIUM-COOLED NUCLEAR POWER REACTORS.

    Published 1970
    Online Access (via OSTI)
    Government Document Electronic eBook
  14. 14

    A CORRELATION OF ROD BUNDLE CRITICAL HEAT FLUX FOR WATER IN THE PRESSURE RANGE 150 TO 725 PSIA.

    Published 1970
    Online Access (via OSTI)
    Government Document Electronic eBook
  15. 15

    HIGH TEMPERATURE ULTRASONIC THERMOMETER FOR MEASURING REACTOR FUEL TEMPERATURE.

    Published 1970
    Online Access (via OSTI)
    Government Document Electronic eBook
  16. 16

    SPERT PROJECT QUARTERLY TECHNICAL REPORT, JANUARY-MARCH 1964

    Published 1964
    Online Access (via OSTI)
    Government Document Electronic eBook
  17. 17
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  19. 19
  20. 20

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

    Published 1986
    Online Access (via OSTI)
    Government Document Electronic eBook
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