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  • Heat transfer in rod bundles; [papers]

    • Text
    • New York, American Society of Mechanical Engineers [1968]
    • 1968
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 85-515Offsite

  • Analysis of KS-1 experimental data on the behavior of the heated rod temperatures in the partially uncovered VVER core model using RELAP5/MOD3.2 [microform] / prepared by V.A. Vinogradov, A.Y. Balykin.

    • Text
    • Washington, DC : U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1999]
    • 1999

  • Application of RELAP5/MOD3.1 to ATWS analysis of control rod withdrawal from 1% power level [microform] / prepared by H. Kantee.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : [Supt. of Docs., U.S. G.P.O., distributor, 2000]
    • 2000

  • Data summary report for fission product release test VI-1 / prepared by M.F. Osborne ... [et al.].

    • Text
    • Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989

  • Maximum temperature calculation and operational characteristics of fuel follower control rods for the AFRRI TRIGA reactor facility [microform] / M. Forsbacka, M. Moore.

    • Text
    • Bethesda, Md. : Defense Nuclear Agency, Armed Forces Radiobiology Research Institute, [1991]
    • 1991

  • Assessment of CCFL model of RELAP5/MOD3 against simple verticle tubes and rod bundle tests [microform] / prepared by S. Cho ... [et al.].

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Available from Supt. of Docs., U.S. G.P.O. ; Springfield, VA : National Technical Information Service [distributor, 1993]
    • 1993

  • Data summary report for fission product release test VI-2 [microform] / prepared by M.F. Osborne ... [et al.].

    • Text
    • Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989

  • Compendium of ECCS research for realistic LOCA analysis : final report.

    • Text
    • Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
    • 1988

  • Data summary report for fission product release test VI-6 [microform] / prepared by M.F. Osborne ... [et al.].

    • 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], 1994.
    • 1994

  • Radiological characterization of spent control rod assemblies [microform] / prepared by E.A. Lepel ... [et al.].

    • 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], 1995.
    • 1995

  • Department of Energy's Hanford spent nuclear fuel project : hearing before the Subcommittee on Oversight and Investigations of the Committee on Commerce, House of Representatives, One Hundred Fifth Congress, second session, May 12, 1998.

    • Text
    • Washington : U.S. G.P.O. : For sale by the U.S. G.P.O., Supt. of Docs., Congressional Sales Office, 1998.
    • 1998

  • FRAPCON-3 [microform].

    • Text
    • Wasington, DC : Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1997.
    • 1997

  • Modification of USNRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel [microform] / prepared by A. Shestopalov ... [et al.].

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1999]
    • 1999

  • Modification of IPSN's SCANAIR fuel rod transient code for high burnup VVER fuel [microform] / prepared by K. Mikitiouk ... [et al.].

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1999]
    • 1999

  • Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity accident conditions [microform].

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1999]
    • 1999

  • Analysis of pin-by-pin effects for LWR rod ejection accident [microform] / prepared by A. Avvakumov, V. Maloveev, V. Sidorov.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 2000]
    • 2000

  • Transportation of spent rods to the proposed Yucca Mountain storage [i.e. storage facility] : hearing before the Subcommittees on Highways and Transit and Railroads of the Committee on Transportation and Infrastructure, House of Representatives, One Hundred Seventh Congress, second session, April 25, 2002.

    • Text
    • Washington : U.S. G.P.O. : For sale by the Supt. of Docs., U.S. G.P.O. [Congressional Sales Office], 2002.
    • 2002

  • A new comparative analysis of LWR fuel designs [microform] / prepared by G.M. O'Donnell, H.H. Scott, R.O. Meyer.

    • Text
    • Washington, DC : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 2001.
    • 2001

  • Auslegung, Bestrahlung und Nachuntersuchung der UC und (U, Pu)C-Brennstäbe der Versuchsgruppen Mol-11/K1 und Mol-11/K2 / D. Freund ... [et al.].

    • Text
    • Karlsruhe : Kernforschungszentrum Karlsruhe, 1976.
    • 1976
    • 1 Item
    FormatCall NumberItem Location
    Text JBY Q-49Offsite

  • Pellet-clad interaction in water reactor fuels : seminar proceedings, Aix-en-Provence, France, 9-11 March 2004 / hosted by CEA Cadarache, DEN, DEC ; in co-operation with EDF ... [et al.].

    • Text
    • Paris : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, c2005.
    • 2005
    • 1 Item
    FormatCall NumberItem Location
    Text JBF 05-691Offsite

  • Heizstäbe zur Simulation von Brennstäben für Natrium-Siedeexperimente / V. Casal ... [et al.].

    • Text
    • Karlsruhe : Kernforschungszentrum Karlsruhe, 1977.
    • 1977

  • Making mixed oxide lead fuel assemblies for the U.S. plutonium disposition program / National Nuclear Security Administration.

    • Text
    • [Washington, D.C.] : U.S. Dept. of Energy, National Nuclear Security Administration, [2005]
    • 2005
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/LPS109753

  • Fuel fragmentation, relocation, and dispersal during the loss-of-coolant accident / prepared by Patrick. A.C. Raynaud.

    • Text
    • Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2012]
    • 2012
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo22860

  • Mechanical behavior of ballooned and ruptured cladding / prepared by Michelle Flanagan.

    • Text
    • Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2012]
    • 2012
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo22857

  • MTR rods as fission product sources for industrial sterilization : engineering feasibility study and cost estimate. Job 24.

    • Text
    • New York, NY : Vitro Corporation of America, 1954.
    • 1954
    • 1 Item
    FormatCall NumberItem Location
    Text PLE (Vitro Corp. MTR rods as fission product sources)Offsite

  • Fuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE/FRAPTRAN/Dakota codes in SNAP interface / prepared by Chunkuan Shih [and six others].

    • Text
    • Washington, DC : U.S. Nuclear Regulatory Commission, March 2016.
    • 2016-3
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo66696

  • Analysis of KS-1 experimental data on the behavior of the heated rod temperatures in the partially uncovered VVER core model using RELAP5/MOD3.2 / prepared by V.A. Vinogradov, A.Y. Balykin.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, November 1999.
    • 1999-11
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo68850

  • Analysis of pin-by-pin effects for LWR rod ejection accident / prepared by A. Avvakumov, V. Malofeev, V. Sidorov.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, March 2000.
    • 2000-3
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo70159

  • Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity accident conditions.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, July 1999.
    • 1999-7
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo68840

  • A new comparative analysis of LWR fuel designs / prepared by G. M. O'Donnell, H. H. Scott, R. O. Meyer.

    • Text
    • Washington, DC : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.
    • 2001
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo70665

  • Assessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests / prepared by S. Cho [and three others].

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, June 1993.
    • 1993-6
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73917

  • Application of RELAP5/MOD3.1 to ATWS analysis of control rod withdrawal from 1% power level / prepared by H. Kantee.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, June 2000.
    • 2000-6
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo83911

  • Credibility assessment framework for critical boiling transition models : a generic safety case to determine the credibility of crucial heat flux and critical power models / prepared by: J.S. Kaizer [and 7 others].

    • Text
    • [Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, March 2019.
    • 2019-3
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo121643

  • Evaluation of intersubchannel mixing in a simulated nuclear fuel rod bundle using a gamma camera / Alireza Sedaghat-Hamedani.

    • Text
    • 1984.
    • 1984
    • 1 Item
    FormatCall NumberItem Location
    Text FC85- 6037Off-site

  • Evaluation of intersubchannel mixing in a simulated nuclear fuel rod bundle using a gamma camera / Alireza Sedaghat-Hamedani.

    • Text
    • 1984.
    • 1984
    • 1 Item
    FormatCall NumberItem Location
    Text LD1237.5D 1984 .S33Off-site

  • Development and properties of silver-base alloys as control rod materials for pressurized water reactors / I. Cohen.

    • Text
    • Pittsburgh, Pennsylvania : Bettis Atomic Power Laboratory, 1959.
    • 1959
    • 1 Item
    FormatCall NumberItem Location
    Text MICROFILMOff-site

  • Heat transfer in rod bundles; [papers]

    • Text
    • New York, American Society of Mechanical Engineers [1968]
    • 1968
    • 1 Item
    FormatCall NumberItem Location
    Text 9941.8935.1968Off-site

  • Department of Energy's Hanford spent nuclear fuel project : hearing before the Subcommittee on Oversight and Investigations of the Committee on Commerce, House of Representatives, One Hundred Fifth Congress, second session, May 12, 1998.

    • Text
    • Washington : U.S. G.P.O. : For sale by the U.S. G.P.O., Supt. of Docs., Congressional Sales Office, 1998.
    • 1998
    • 1 Item
    FormatCall NumberItem Location
    Text Y 4.C 73/8:105-90Off-site

  • Transportation of spent rods to the proposed Yucca Mountain storage [i.e. storage facility] : hearing before the Subcommittees on Highways and Transit and Railroads of the Committee on Transportation and Infrastructure, House of Representatives, One Hundred Seventh Congress, second session, April 25, 2002.

    • Text
    • Washington : U.S. G.P.O. : For sale by the Supt. of Docs., U.S. G.P.O. [Congressional Sales Office], 2002.
    • 2002
    • 1 Item
    FormatCall NumberItem Location
    Text Y 4.T 68/2:107-77Off-site

  • Pellet-clad interaction in water reactor fuels : seminar proceedings, Aix-en-Provence, France, 9-11 March 2004 / hosted by CEA Cadarache, DEN, DEC ; in co-operation with EDF ... [et al.].

    • Text
    • 2005
    • 1 Item
    FormatCall NumberItem Location
    Text TK9207.5.P45 2005Off-site

  • Development and properties of silver-base alloys as control rod materials for pressurized water reactors / I. Cohen.

    • Text
    • Pittsburgh, Pennsylvania : Bettis Atomic Power Laboratory, 1959.
    • 1959
    • 1 Item
    FormatCall NumberItem Location
    Text MICROFILMOff-site

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