Showing 1 - 20 results of 105 for search '', query time: 0.09s Refine Results
  1. 1

    Design study : sodium modular reactor

    [Place of publication not identified] : Washington, D.C. : General Electric ; Available from the Office of Technical Services, U.S. Dept. of Commerce, 1960
    Format: Government Document Book


  2. 2

    Sodium Reactor Experiment (SRE) shielding evaluation for thermal neutron streaming at reactor vessel coolant pipe penetrations by Anderson, F. D.

    Canoga Park, California : Atomics International, 1959
    Format: Government Document Book


  3. 3

    Corrosion and activity transfer in the SRE primary sodium system by Johnson, H. E.

    Canoga Park, Calif. : Atomics International, A Division of North American Aviation, Inc., 1961
    Format: Government Document Book


  4. 4

    Power and flow ramp stability tests on the SRE by Griffin, C. W.

    Canoga Park, California : Atomics International, 1962
    Format: Government Document Book


  5. 5

    Two-group calculation of the critical core size of the SRE reactor by Fillmore, F. L.

    Canoga Park, California : Atomics International, 1956
    Format: Government Document Book


  6. 6

    Study of SCTI control system

    Canoga Park, Calif. : Atomics International, 1964
    Format: Government Document Book


  7. 7

    Reflected reactor kinetics by Keaten, R. W.

    Canoga Park, California : Atomics International, 1963
    Format: Government Document Book


  8. 8

    Design and development of the safety-rod drop-time test system by Radcliff, J. G.

    Canoga Park, California : Atomics International, 1963
    Format: Government Document Book


  9. 9

    Analysis of power ramps with an analog computer by Carlson, W. J.

    Canoga Park, California : Atomics International, 1964
    Format: Government Document Book


  10. 10

    Development of a process for sodium bonding of EBR-II fuel and blanket elements by Sowa, Edmund S.

    Argonne, Ill. : Argonne National Laboratory, Reactor Engineering Division, 1961
    Format: Government Document Book


  11. 11

    Carburization of austenitic stainless steel in liquid sodium by Anderson, W. J.

    Canoga Park, California : Atomics International, a division of North American Aviation, Inc., 1960
    Format: Government Document Book


  12. 12

    Sodium flow distribution in test fuel assembly P-23B by Taylor, J. P. S.

    Richland, Wash. : [Springfield, Va.] : Dept. of Energy, Hanford Engineering Development Laboratory ; [for sale by the National Technical Information Service], 1978
    Format: Government Document Book


  13. 13

    Feasibility study of a 1000-Mwe sodium-cooled fast reactor.

    [Oak Ridge, Tennessee] : Springfield, Va. : Division of Technical Information, U.S. Atomic Energy Commission ; Available from the Clearinghouse for Federal Scientific and Technical Information, 1966
    Format: Government Document Book


  14. 14

    Preapplication safety evaluation report for the power reactor innovative small module (PRISM) liquid-metal reactor : final report.

    Washington, DC : Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1994
    Format: Government Document Book


  15. 15

    Simplified formulas and curves for bellows analysis by Winborne, R. A.

    Washington, D.C. : Office of Technical Services, 1964
    Format: Government Document Book


  16. 16

    The non-linear behavior of large permanent-magnet flowmeters by Turner, G. E.

    Canoga Park, California : Washington, D.C. : Atomics International, A Division of North American Aviation, Inc. ; Available from the Office of Technical Services, 1960
    Format: Government Document Book


  17. 17

    10 MWe sodium deuterium reactor design report by Davis, Peter J.

    Oak Ridge, Tenn. : Technical Information Service, 1959
    Format: Government Document Book


  18. 18

    The experimental development of a fuel handling system for the Sodium Reactor Experiment by Hallett, W. J., Leppard, J. A.

    Canoga Park, California : Atomics International, 1958
    Format: Government Document Book


  19. 19

    An evaluation of reactor concepts for use as separate steam superheaters by Lennox, D. H.

    Argonne, Ill. : Argonne National Laboratory, Reactor Engineering Division, 1961
    Format: Government Document Book


  20. 20

    Preliminary test of natural-circulation double-tube steam generator by Welsh, R. D.

    Canoga Park, Calif. : Atomics International, 1959
    Format: Government Document Book