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  1. 1
    Assessment of channel coolant voiding in RD-14M test facility using TRACE /

    Assessment of channel coolant voiding in RD-14M test facility using TRACE / by Oussoren, Andrew, Delja, Aleksandar

    Published 2014
    “…U.S. Nuclear Regulatory Commission,…”
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  2. 2
    Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA /

    Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA / by Wang, Jong-Rong

    Published 2014
    “…U.S. Nuclear Regulatory Commission,…”
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  3. 3
    RELAP5/MOD3.3 assessment by comparison with PKL III G3.1 experiment (small break in the main steam line) /

    RELAP5/MOD3.3 assessment by comparison with PKL III G3.1 experiment (small break in the main steam line) / by Zaruba, A., Krezeminski, K., Benkert, A.

    Published 2014
    “…U.S. Nuclear Regulatory Commission,…”
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  4. 4
    Post-test analysis of Upper Plenum 11% break at PSB-VVER facility using TRACE v5.0 and RELAP5/MOD3.3 code /

    Post-test analysis of Upper Plenum 11% break at PSB-VVER facility using TRACE v5.0 and RELAP5/MOD3.3 code / by Heralecky, P. (Petr)

    Published 2014
    “…U.S. Nuclear Regulatory Commission,…”
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  5. 5
    The establishment and assessment of Chinshan (BWR/4) Nuclear Power Plant TRACE/SNAP model /

    The establishment and assessment of Chinshan (BWR/4) Nuclear Power Plant TRACE/SNAP model / by Wang, Jong-Rong

    Published 2014
    “…U.S. Nuclear Regulatory Commission,…”
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  6. 6
    TRACE/SNAP model establishment of Chinshan nuclear power plant for ultimate response guideline /

    TRACE/SNAP model establishment of Chinshan nuclear power plant for ultimate response guideline / by Wang, Jong-Rong

    Published 2017
    “…Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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