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  • Assessment of RELAP5/MOD3.2 for thermohydraulic processes in heated rod bundles with tight lattice at CKTI test facility / prepared by A. S. Devkin.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, October 1999.
    • 1999-10
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo69989

  • 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

  • RELAP5/MOD2 calculations of OECD LOFT test LP-SB-2 / prepared by P.C. Hall.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 1990.
    • 1990-4
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo72986

  • RELAP5/MOD2 assessment, OECD-LOFT small break experiment LP-SB-03 / prepared by S. Guntay.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 1990.
    • 1990-4
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo72996

  • TRAC-PF1 MOD1 post test calculations of the OECD LOFT experiment LP-SB-1 / prepared by E.J. Allen.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 1990.
    • 1990-4
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73011

  • TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6 / prepared by P. Coddington, C. Gill.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 1992.
    • 1992-4
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73250

  • Analysis of LOBI test BLO2 (three percent cold leg break) with RELAP5 code / prepared by A.H. Scriven.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
    • 1992
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73287

  • RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-03 / prepared by F. D'Auria, M. Frogheri, W. Giannoti.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, February 1999.
    • 1999-2
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73431

  • RELAP5/MOD.2 post test analysis and accuracy quantification of Lobi test BL-34 / prepared by F. D'Auria, M. Frogheri, W. Giannoti.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, February 1999.
    • 1999-2
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73429

  • RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44 / prepared by F. D'Auria, M. Frogheri, W. Giannoti.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, February 1999.
    • 1999-2
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73438

  • Study of transients related to AMSAC actuation, sensitivity analysis / prepared by J.M. Posada [and four others].

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, November 1998.
    • 1998-11
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73426

  • A study of the dispersed flow interfacial heat transfer model of RELAP5/MOD2.5 and RELAP5/MOD3 / prepared by M. Andreani, G. Th. Analytis, S.N. Aksan.

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

    Available Online

    https://purl.fdlp.gov/GPO/gpo73415

  • Test LOBI-BL06 : post-test analysis and RELAP5/MOD3.2.1 code performance assessment / prepared by T. Fiore, P. Marsili.

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

    Available Online

    https://purl.fdlp.gov/GPO/gpo73411

  • RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-04 / prepared by F. D'Auria, M. Frogheri, W. Giannotti.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, February 1999.
    • 1999-2
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73397

  • Analysis of the UPTF separate effects test 11 (steam-water countercurrent flow in the broken loop hot leg) using RELAP5/MOD2 / prepared by M.J. Dillistone.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, June 1992.
    • 1992-6
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73711

  • LOFT input dataset reference document for RELAP5 validation studies / prepared by J.C. Birchley.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 1992.
    • 1992-4
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73709

  • Time step and mesh size dependencies in the heat conduction solution of a semi-implicit, finite difference scheme for transient two-phase flow / prepared by R. O'Mahoney.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 1992.
    • 1992-4
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73713

  • Assessment of RELAP5/MOD2 cycle 36.04 with LOFT large break LOCE L2-3 / prepared by Y.S. Bang, H.J. Kim, S.H. Kim.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 1992.
    • 1992-4
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73706

  • Assessment of RELAP5/MOD2 cycle 36.04 using LOFT intermediate break experiment L5-1 / prepared by E.J. Lee, B.D. Cung, H.J. Kim.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 1992.
    • 1992-4
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73705

  • Assessment of the "one feedwater pump trip transient" in Cofrentes Nuclear Power Plant with TRAC-BF1 / prepared by F. Castrillo, A.G. Navarro, I. Gallego.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 1992.
    • 1992-4
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73703

  • RELAP5/MOD2 analysis of LOFT experiment L9-4 / prepared by M.B. Keevill.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
    • 1992
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73694

  • Analysis of semiscale test S-LH-1 using RELAP5/MOD2 / prepared by P.C. Hall, D.R. Bull.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
    • 1992
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73689

  • Recirculation suction large break LOCA analysis of the Santa Maria De Garoña nuclear power plant using TRAC-BF1 (G1J1) / prepared by J.V. López, J. L. Crespo, R. A. Fernandez.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, August 1992.
    • 1992-8
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73696

  • Analysis of semiscale test S-LH-2 using RELAP5/MOD2 / prepared by P. Brodie, P.C. Hall.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
    • 1992
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73688

  • Assessment of RELAP5/MOD2 using the test data of REWET-II reflooding experiment SGI/R / prepared by A. Hämäläinen.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, May 1993.
    • 1993-5
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73874

  • Assessment of RELAP5/MOD2 against a natural circulation experiment in nuclear power plant Borssele / prepared by L. Winters.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, July 1993.
    • 1993-7
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73875

  • Assessment of RELAP5/MOD2 computer code against the net load trip test data from Yong-Gwang, unit 2 / prepared by Namsung Arne, Sungjae Cho, Sang Hoon Lee.

    • 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/gpo73876

  • RELAP5/MOD3 assessment for calculation of safety and relief valve discharge piping hydrodynamic loads / prepared by E.J. Stubbe, L. VanHoenacker, R. Otero.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, February 1994.
    • 1994-2
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73880

  • Assessment of RELAP5/MOD3 against twenty-five post-dryout experiments performed at the Royal Institute of Technology / prepared by Lars Nilsson.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, May 1993.
    • 1993-5
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73886

  • RELAP5 assessment using LSTF test data SB-CL-18 / prepared by S. Lee, B.D. Chung, H.J. Kim.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, May 1993.
    • 1993-5
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo73891

  • RELAP5 assessment using semiscale SBLOCA test S-NH-1 / prepared by Euy-Joon Lee, Bub-Dong Chung, Hho-Jung Kim.

    • 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/gpo73913

  • 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

  • Assessment of BETHSY test 9.1.b using RELAP5/MOD3 / prepared by S. Lee, B. D. Chung, H. J. Kim.

    • 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/gpo73925

  • Numerics and implementation of the UK horizontal stratification entrainment off-take model into RELAP5/MOD3 / prepared by W. M. Bryce.

    • 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/gpo73896

  • Development, implementation, and assessment of specific closure laws for inverted-annular film-boiling in a two-fluid model / prepared by François de Cachard.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, October 1996.
    • 1996-10
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo82895

  • Post-test examination results from integral, high-burnup, fueled LOCA tests at Studsvik Nuclear Laboratory / Michelle E. Flanagan, Peter Askeljung, Anders Puranen.

    • Text
    • Washington, D.C. : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2013.
    • 2013
    • 1 Resource

    Available Online

    https://purl.fdlp.gov/GPO/gpo40353

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