Research Catalog

  • Proceedings.

    • Text
    • London, Institution of Mechanical Engineers, 1961.
    • 1961
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 73-529Offsite
  • Gasgekühlte Hochtemperaturreaktoren. Gas-cooled high-temperature reactor.

    • Text
    • München, K. Thiemig [c1972]
    • 1972
    • 1 Item
    FormatCall NumberItem Location
    Text JSC 73-186Offsite
  • Nuclear gas turbines; proceedings of the international conference organized by the British Nuclear Energy Society in London, 8-9 April 1970.

    • Text
    • London, British Nuclear Energy Society, 1970.
    • 1970
    • 1 Item
    FormatCall NumberItem Location
    Text JSG 75-100Offsite
  • Physics of high-temperature reactors / by Luigi Massimo. 1st ed.

    • Text
    • Oxford ; New York : Pergamon Press, 1975.
    • 1975
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 76-460Offsite
  • The High temperature reactor and process applications : proceedings of the international conference organized by the British Nuclear Energy Society in London, 26-28 November 1974.

    • Text
    • London : Thomas Telford Ltd. [for] the British Nuclear Energy Society, 1975.
    • 1975
    • 1 Item
    FormatCall NumberItem Location
    Text JSG 77-109Offsite
  • Gas-cooled reactors with emphasis on advanced systems; proceedings.

    • Text
    • Vienna, International Atomic Energy Agency, 1976.
    • 1976
    • 2 Items
    FormatCall NumberItem Location
    Text JSK 77-136 Library has: Vol. 1-2. v. 1Offsite
    FormatCall NumberItem Location
    Text JSK 77-136 Library has: Vol. 1-2. v. 2Offsite
  • Thermal and flow design of helium-cooled reactors / Gilbert Melese, Robert Katz ; prepared under the direction of the American Nuclear Society for the U.S. Department of Energy.

    • Text
    • La Grange Park, Ill., USA : American Nuclear Society, c1984.
    • 1984
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 86-932Offsite
  • Auslegungsvorschläge für Deckenreflektoren mittelgrosser Hochtemperaturreaktoren am Beispiel des HTR-500 / Jan Christoph Otten.

    • Text
    • Jülich, Bundesrepublik Deutschland : Forschungszentrum Jülich, Zentralbibliothek, 1991.
    • 1991
    • 1 Item
    FormatCall NumberItem Location
    Text JSG 91-115Offsite
  • Gao wen qi leng dui / Gao Wen bian zhu.

    • Text
    • Beijing : Yuan zi neng chu ban she : Xin hua shu dian Beijing fa xing suo fa xing, 1982.
    • 1982
    • 1 Item
    FormatCall NumberItem Location
    Text *OVL 86-1582Offsite
  • The design of gas-cooled graphite-moderated reactors.

    • Text
    • London, New York, Oxford University Press, 1963.
    • 1963
    • 1 Item
    FormatCall NumberItem Location
    Text PAWF (Poulter, D. R. Design of gas-cooled graphite-moderated reactors) 1963Offsite
  • Technology of the gas-cooled power reactor and related subjects. Papers presented by the U.K.A.E.A. to the Second United Nations Conference on the Peaceful Uses of Atomic Energy, 1st-13th September 1958.

    • Text
    • [London] 1958.
    • 1958
    • 1 Item
    FormatCall NumberItem Location
    Text PAWF (Great Britain. United Kingdom atomic energy authority. Technology of the gas-cooled power reactor) 1958Offsite
  • High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation quarterly progress report [microform] / prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research ; prepared by the Oak Ridge National Laboratory.

    • Text
    • Washington, D.C. : The Office : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : Available from National Technical Information Service
    • 1982-present
  • Safety aspects of forced flow cooldown transients in modular high temperature gas-cooled reactors [microform] / prepared by P.G. Kroger.

    • Text
    • 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, 1993]
    • 1993
  • Code and model extensions of the THATCH code for modular high temperature gas-cooled reactors [microform] / prepared by P.G. Kroger, R.J. Kennett.

    • Text
    • 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, 1993]
    • 1993
  • MORECA-2 [microform] : interactive simulator for modular high-temperature gas-cooled reactor core transients and heatup accidents with ATWS options / prepared by S.J. Ball, D.J. Nypaver.

    • Text
    • 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.
    • 1992
  • Magnitude and reactivity consequences of moisture ingress into the modular high-temperature gas-cooled reactor core [microform] / prepared by O.L. Smith.

    • Text
    • 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.
    • 1992
  • Evaluation of MHTGR fuel reliability [microform] / prepared by R.P. Wichner, W.P. Barthold.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992.
    • 1992
  • MORECA, a computer code for simulating modular high-temperature gas-cooled nuclear reactor core heatup accidents [microform] / prepared by S.J. Ball.

    • Text
    • Washington, DC : Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1991.
    • 1991
  • Fission product plateout and liftoff in the MHTGR primary system : a review / prepared by R.P. Wichner.

    • Text
    • Washington, DC : Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1991.
    • 1991
  • Modeling and performance of the MHTGR reactor cavity cooling system [microform] / prepared by J.C. Conklin.

    • Text
    • Washington, DC : Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
    • 1990
  • Scoping calculations of power sources for nuclear electric propulsion [microform] / F.C. Difilippo.

    • Text
    • Oak Ridge, Tenn. : ORNL, Oak Ridge National Laboratory ; [Washington, DC : National Aeronautics and Space Administration ; Springfield, Va., : National Technical Information Center, distributor, 1994]
    • 1994
  • Basic studies in the field of high-temperature engineering : second information exchange meeting, Paris, France, 10-12 October 2001 / co-organized by the Japan Atomic Energy Research Institute.

    • Text
    • Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, c2002.
    • 2002
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 02-1007Offsite
  • Basic studies in the field of high-temperature engineering : third information exchange meeting, Ibaraki-ken, Japan, 11-12 September 2003 / co-organized by the Japan Atomic Energy Research Institute.

    • Text
    • Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, c2004.
    • 2004
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 04-603Offsite
  • Gas-cooled fast reactor.

    • Text
    • [Idaho Falls, Idaho] : Idaho National Laboratory, [2007?]
    • 2007
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/LPS103451
  • Accident analysis for nuclear power plants with modular high temperature gas cooled reactors / International Atomic Energy Agency.

    • Text
    • Vienna, Austria : International Atomic Energy Agency, 2008.
    • 2008
    • 1 Item

    Available Online

    http://www-pub.iaea.org/MTCD/publications/PDF/pub1318_web.pdf
    FormatCall NumberItem Location
    Text JSE 09-56Offsite
  • Gas-cooled reactors ; proceedings.

    • Text
    • Lancaster, Pa., 1960.
    • 1960
    • 1 Item
    FormatCall NumberItem Location
    Text VBA (Franklin Institute, Philadelphia. Journal. Monograph, 4) v. 4-7 (1958-60)Offsite
  • Gas cooled reactor design and safety.

    • Text
    • Vienna : International Atomic Energy Agency, 1990.
    • 1990
    • 1 Item
    FormatCall NumberItem Location
    Text HD9698.A1 I6 no.312Off-site
  • Advanced and high-temperature gas-cooled reactors. : Proceedings of a symposium ... / held by the International Atomic Energy Agency, 21-25 Oct. 1968.

    • Text
    • Vienna : International Atomic Energy Agency, 1969.
    • 1969
    • 1 Item
    FormatCall NumberItem Location
    Text TK9203.G3 S87 1968Off-site
  • Gas-cooled reactors ; proceedings.

    • Text
    • Lancaster, Pa., 1960.
    • 1960
    • 1 Item
    FormatCall NumberItem Location
    Text TK9203.G3 Sy68 1960Off-site
  • Thermal and flow design of helium-cooled reactors / Gilbert Melese, Robert Katz ; prepared under the direction of the American Nuclear Society for the U.S. Department of Energy.

    • Text
    • La Grange Park, Ill., USA : American Nuclear Society, [1984], ©1984.
    • 1984-1984
    • 1 Item
    FormatCall NumberItem Location
    Text TK9203.G3 M45 1984Off-site
  • Refuelling of gas-cooled reactors / a symposium arranged by the Nuclear Energy Group of the Institution of Mechanical Engineers, 12th December 1968.

    • Text
    • London : Institution of Mechanical Engineers, 1969.
    • 1969
    • 1 Item
    FormatCall NumberItem Location
    Text TJ1 .In811 v.183G:pt.3Off-site
  • Conceptual design of a fluidized bed nuclear reactor : statics, dynamics, and safety-related aspects / Alexander Agung.

    • Text
    • Amsterdam : IOS Press, [2007], ©2007.
    • 2007-2007
    • 1 Item
    FormatCall NumberItem Location
    Text TK9203.G3 A49 2007Off-site
  • Proceedings of the Japan - U.S. seminar on HTGR safety technology : September 15-16, 1977, Brookhaven National Laboratory, Upton, N. Y. / sponsored by Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.

    • Text
    • Washington : Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research ; Springfield, Va. : for sale by the National Technical Information Service, 1978.
    • 1978
    • 2 Items
    FormatCall NumberItem Location
    Text TK9203.G3 J3 1978 v.1Off-site
    FormatCall NumberItem Location
    Text TK9203.G3 J3 1978 v.2Off-site
  • Thorium and gas cooled reactors : a seminar for the 65th birthday of Dr. Peter Fortescue, held at General Atomic Company, San Diego, California, USA, 17 June 1978 / edited by J. P. Howe and G. Melese-d'Hospital.

    • Text
    • Oxford ; New York : Pergamon Press, c1978.
    • 1978
    • 1 Item
    FormatCall NumberItem Location
    Text TK9203.G3 T48 1978Off-site
  • Dissociating gases as heat-transfer media and working fluids in power installations : (materials of the all-union conference) / Edited by A. K. Krasin.

    • Text
    • New Delhi : Published for the Atomic Energy Commission and the National Sciences Foundation, Washington, D.C., by Amerind Publishing Co., 1975.
    • 1975
    • 1 Item
    FormatCall NumberItem Location
    Text TK9203.G3xD5813Off-site
  • The design of gas-cooled graphite-moderated reactors.

    • Text
    • London, New York, Oxford University Press, 1963.
    • 1963
    • 1 Item
    FormatCall NumberItem Location
    Text 9936.734Off-site
  • Gas-cooled reactors; proceedings.

    • Text
    • Lancaster, Pa., 1960.
    • 1960
    • 1 Item
    FormatCall NumberItem Location
    Text 9936.361Off-site
  • Semi-homogeneous high-temperature gas-cooled breeder reactors / by K. Inoue, T. Kuroyanagi, S. Yajima.

    • Text
    • [Oak Ridge, Tenn.] : U.S. Atomic Energy Commission, Technical Information Service, [between 1959 and 1962]
    • 1958-1962
    • 1 Item
    FormatCall NumberItem Location
    Text 9936.489Off-site
  • Basic studies in the field of high-temperature engineering : second information exchange meeting, Paris, France, 10-12 October 2001 / co-organized by the Japan Atomic Energy Research Institute.

    • Text
    • Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, c2002.
    • 2002
    • 1 Item
    FormatCall NumberItem Location
    Text TK9203.G3 B37 2002Off-site
  • Basic studies in the field of high-temperature engineering : third information exchange meeting, Ibaraki-ken, Japan, 11-12 September 2003 / co-organized by the Japan Atomic Energy Research Institute (JAERI).

    • Text
    • Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, c2004.
    • 2004
    • 1 Item
    FormatCall NumberItem Location
    Text TK9203.G3 B37 2003Off-site
  • Dissociating gases as heat-transfer media and working fluids in power installations : (materials of the all-union conference) / Edited by A. K. Krasin.

    • Text
    • New Delhi : Published for the Atomic Energy Commission and the National Sciences Foundation, Washington, D.C., by Amerind Publishing Co., 1975.
    • 1975
    • 1 Item
    FormatCall NumberItem Location
    Text TK9203.G3xD5813Off-site
  • Semi-homogeneous high-temperature gas-cooled breeder reactors / by K. Inoue, T. Kuroyanagi, S. Yajima.

    • Text
    • [Oak Ridge, Tenn.] : U.S. Atomic Energy Commission, Technical Information Service, [between 1959 and 1962]
    • 1958-1962
    • 1 Item
    FormatCall NumberItem Location
    Text 9936.489Off-site
  • Basic studies in the field of high-temperature engineering : second information exchange meeting, Paris, France, 10-12 October 2001 / organized by the Nuclear Science Committee of the OECD Nuclear Energy Agency and the Japan Atomic Energy Research Institute.

    • Text
    • Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, ©2002.
    • 2002
    • 1 Item
    FormatCall NumberItem Location
    Text TK9203.G3 B37 2002Off-site

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