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1
An integral analysis of heat transfer downstream of a rearward-facing step with small coolant injection.
by Karashima, Keiichi, 1933-
Washington, National Aeronautics and Space Administration; [for sale by the Clearinghouse for Federal Scientific and Technical Information, Springfield, Va.] 1970

Government Document Book
2
Closed form equations for the preliminary design of a heat-pipe-cooled leading edge /
by Glass, David E.
Hampton, Va. : Springfield, VA : National Aeronautics and Space Administration, Langley Research Center ; National Technical Information Service, distributor, 1998

Government Document Book
3
Multiloop integral system test (MIST) : final report /
Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : For sale by the Supt. of Docs., U.S. G.P.O., 1989

Government Document Book
4
Reactor Development Program Progress Report January 1966 /
by Crewe, Albert V.
Argonne, Ill. : Argonne National Laboratory, 1966

Book
5
Nineteenth Annual IEEE Semiconductor Thermal Measurement and Management Symposium : SEMI-THERM proceedings 2003 : San Jose, CA, USA, March 11-13, 2003 /
Piscataway, N.J. : IEEE, 2003

This item is not available through EZBorrow. Please contact your institution’s interlibrary loan office for further assistance.
Conference Proceeding Book
6
Probability of pipe failure in the reactor coolant loops of Babcock and Wilcox PWR plants.
Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1985

Government Document Book
7
Flow in rotating serpentine coolant passages with skewed trip strips : under contract NAS3-27378 /
by Tse, David G. N.
[Washington, DC] : [Springfield, Va.] : [National Aeronautics and Space Administration] ; [National Technical Information Service, distributor], 1996

Government Document Book
8
Multiloop integral system test (MIST) : final report /
Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : For sale by the Supt. of Docs., U.S. G.P.O., 1989

Government Document Book
9
Assessment of RELAP5/MOD2 critical flow model using Marviken test data 15 and 24 /
by Kim, K.
Washington, DC : Springfield, VA : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Available from Supt. of Docs., U.S. G.P.O. ; National Technical Information Service [distributor], 1992

Government Document Book
10
Hot carrier dynamics in the X valley in Si and Ge measured by pump-IR-probe absorption spectroscopy /
by Wang, W. B.
[Washington, DC] : [Springfield, Va.] : [National Aeronautics and Space Administration] ; [National Technical Information Service, distributor], 1996

Government Document Book
11
Reactor Development Program Progress Report March 1969 /
by Duffield, Robert B.
Argonne, Ill. : Argonne National Laboratory, 1969

Book
12
Reactor Development Program Progress Report September 1966 /
by Crewe, Albert V.
Argonne, Ill. : Argonne National Laboratory, 1966

Book
13
Reactor Development Program Progress Report December 1967 /
by Duffield, Robert B.
Argonne, Ill. : Argonne National Laboratory, 1968

Book
14
Reactor Development Program Progress Report. February 1965 /
by Crewe, Albert V.
Argonne, Ill. : Argonne National Laboratory, 1965

Government Document Book
15
Reactor Development Program Progress Report September 1967 /
by Manning, Winston M.
Argonne, Ill. : Argonne National Laboratory, 1967

Book
16
Analysis of heat transfer in a porous cooled wall with variable pressure and temperature along the coolant exit boundary /
by Siegel, Robert, 1927-
Washington, D.C. : [Springfield, Va.] : National Aeronautics and Space Administration ; [For sale by the National Technical Information Service], 1972

Government Document Book
17
VICTORIA : a mechanistic model of radionuclide behavior in the reactor coolant system under severe accident conditions /
Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992
Rev. 1.

Government Document Book
18
Technical support for a proposed decay heat guide using SAS2H/ORIGEN-S data /
by Hermann, O. W.
Washington, DC : U.S. Nuclear Regulatory Commission, 1994

Government Document Book
19
Technical findings related to generic issue 23 : reactor coolant pump seal failure /
by Ruger, C. J.
Washington, D.C. : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989

Government Document Book
20
Convective array cooling for a solar powered aircraft /
by Colozza, Anthony J.
[Cleveland, Ohio] : Hanover, MD : National Aeronautics and Space Administration, Glenn Research Center ; Available from NASA Center for Aerospace Information, 2003

Government Document Book
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