Showing 1 - 20 results of 23 for search 'Argonne National Laboratory. Reactor Analysis and Safety Division', query time: 0.08s Refine Results
  1. 1
    Contribution to the theory of the two phase blowdown phenomenon

    Contribution to the theory of the two phase blowdown phenomenon by Hutcherson, Michael N.

    Argonne, Ill. : Reactor Analysis and Safety Division, Argonne National Laboratory, 1975
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Book


    Save to List
    Saved in:
  2. 2
    Multichannel clad-relocation model for fast-reactor loss-of-flow accidents

    Multichannel clad-relocation model for fast-reactor loss-of-flow accidents by Ishii, M.

    Argonne, Ill. : [Springfield, Va.] : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory ; [for sale by the National Technical Information Service], 1979
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  3. 3
    Pressure-pulse propagation in two-phase one- and two-component mixtures

    Pressure-pulse propagation in two-phase one- and two-component mixtures by Henry, Robert E.

    Argonne, Ill. : Reactor Analysis and Safety Division, Argonne National Laboratory, 1971
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Book


    Save to List
    Saved in:
  4. 4
    Test E3 on high-energy transient meltdown of irradiated UO₂ in a TREAT Mark-II loop

    Test E3 on high-energy transient meltdown of irradiated UO₂ in a TREAT Mark-II loop

    Argonne, Ill. : [Springfield, Va.] :; Argonne, Ill. : [Springfield, Va.] : Dept. of Energy, Argonne National Laboratory ; [for sale by the National Technical Information Service],; Dept. of Energy, Argonne National Laboratory ; [For sale by the National Technical Information Service], 1977
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  5. 5
    PROSA-1 : a probabilistic response-surface analysis code

    PROSA-1 : a probabilistic response-surface analysis code by Vaurio, J. K.

    Argonne, Ill. : [Springfield, Va.] : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory ; [for sale by the National Technical Information Service], 1978
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  6. 6
    The role of bubble-size equilibration in the transient behavior of fission gas

    The role of bubble-size equilibration in the transient behavior of fission gas by Gruber, E. E. (Eugene E.), 1933-

    Argonne, Ill. : Springfield, Va. : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory ; For sale by the National Technical Information Service, 1978
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  7. 7
    The dynamic response of cracked hexagonal subassembly ducts

    The dynamic response of cracked hexagonal subassembly ducts by Glazik, J. L.

    Argonne, Ill. : Springfield, Va. : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory ; For sale by the National Technical Information Service, 1979
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  8. 8
    Coupled hydrodynamic-structural response analysis of piping systems

    Coupled hydrodynamic-structural response analysis of piping systems by A-Moneim, M. T.

    Argonne, Ill. : Oak Ridge, Tenn. : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory ; For sale by the Dept. of Energy, Technical Information Center, 1978
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  9. 9
    F1 phenomenological test on fuel motion : final report

    F1 phenomenological test on fuel motion : final report

    Argonne, Ill. : [Springfield, Va.] : Dept. of Energy, Argonne National Laboratory ; [for sale by the National Technical Information Service], 1978
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  10. 10
    On the incipient boiling of sodium and its application to reactor system

    On the incipient boiling of sodium and its application to reactor system by Holtz, Robert E. (Robert Edward)

    Argonne, Ill. : Reactor Analysis and Safety Division, Argonne National Laboratory, 1971
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Book


    Save to List
    Saved in:
  11. 11
    ALICE, a hybrid Lagrangian-Eulerian code for calculating fluid-structure interaction transients in fast-reactor containment

    ALICE, a hybrid Lagrangian-Eulerian code for calculating fluid-structure interaction transients in fast-reactor containment by Chu, Han Y.

    Argonne, Ill. : [Springfield, Va.] : Dept. of Energy, Argonne National Laboratory ; [for sale by the National Technical Information Service], 1979
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  12. 12
    Liquid-liquid contact in vapor explosion

    Liquid-liquid contact in vapor explosion by Segev, Aryeh

    Argonne, Ill. : [Springfield, Va.] : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory ; [for sale by the National Technical Information Service], 1978
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  13. 13
    Summary of treat experiments on oxide core-disruptive accidents

    Summary of treat experiments on oxide core-disruptive accidents

    Argonne, Ill. : [Springfield, Va.] : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory ; [for sale by the National Technical Information Service], 1979
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  14. 14
    LIMBO computer code for analyzing coolant-voiding dynamics in LMFBR safety tests

    LIMBO computer code for analyzing coolant-voiding dynamics in LMFBR safety tests by Bordner, G. L.

    Argonne, Ill. : [Springfield, Va.] : Dept. of Energy, Argonne National Laboratory ; [for sale by the National Technical Information Service], 1979
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  15. 15
    Loss-of-flow test L5 on FFTF-type irradiated fuel

    Loss-of-flow test L5 on FFTF-type irradiated fuel

    Argonne, Ill. : Springfield, Va. : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory : For sale by the National Technical Information Service, 1978
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  16. 16
    Transient energy transfer by conduction and radiation for a sudden contact between molten UO2 and sodium

    Transient energy transfer by conduction and radiation for a sudden contact between molten UO2 and sodium by Cho, D. H.

    Argonne, Ill. : Springfield, Va. : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory ; For sale by the National Technical Information Service, 1978
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  17. 17
    A study of the transient correction factor used in TREAT reactor in-pile experiments

    A study of the transient correction factor used in TREAT reactor in-pile experiments by Graff, Dale L.

    Argonne, Ill. : Springfield, Va. : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory ; For sale by the National Technical Information Service, 1978
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  18. 18
    Transient-overpower test E8 on FFTE-type low-power-irradiated fuel

    Transient-overpower test E8 on FFTE-type low-power-irradiated fuel

    [Argonne, Ill.] : Springfield, Va. : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory ; For sale by the National Technical Information Service, 1977
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  19. 19
    Theory and application of a quasi-Eulerian fluid element for the STRAW code

    Theory and application of a quasi-Eulerian fluid element for the STRAW code by Kennedy, J. M. (James M.), 1928-

    Argonne, Ill. : [Springfield, Va.] : Dept. of Energy, [Office of Energy Research], Argonne National Laboratory ; [for sale by the National Technical Information Service], 1978
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:
  20. 20
    Plane-strain stress intensity factors for cracked hexagonal subassembly ducts

    Plane-strain stress intensity factors for cracked hexagonal subassembly ducts by Petroski, H. J.

    Argonne, Ill. : [Springfield, Va.] : Dept. of Energy, Argonne National Laboratory ; [for sale by the National Technical Information Service], 1977
    “…Argonne National Laboratory. Reactor Analysis and Safety Division…”
    Format: Government Document Book


    Save to List
    Saved in:

Search Tools: