Search Results - "Heidet, F."

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  1. 1

    CORE DESIGN ACTIVITIES OF THE VERSATILE TEST REACTOR – CONCEPTUAL PHASE by Heidet, F., Roglans-Ribas, J.

    Published in EPJ Web of conferences (01-01-2021)
    “…The Versatile Test Reactor (VTR) is a new fast spectrum test reactor being developed in the United States under the direction of the US Department of Energy,…”
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    Journal Article
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    VERIFICATION OF THE DIFFUSION AND TRANSPORT SOLVERS WITHIN DIF3D FOR 3D HEXAGONAL GEOMETRIES by Nelson, A. G., Smith, M. A., Heidet, F.

    Published in EPJ Web of conferences (01-01-2021)
    “…The DIF3D code (DIFfusion 3D) has been a workhorse of fast reactor analysis work at Argonne National Laboratory for over 40 years. DIF3D was primarily built in…”
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    Journal Article
  3. 3

    IMPACT OF NUCLEAR DATA LIBRARIES ON PREDICTED FAST REACTOR PERFORMANCE by Nelson, A.G., Ramey, K.M., Heidet, F.

    Published in EPJ Web of conferences (2021)
    “…The nuclear data evaluation process inherently yields a nuclear data set designed to produce accurate results for the neutron energy spectra corresponding to a…”
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    MSRE TRANSIENT BENCHMARKS USING SAM by Fei, T., Hua, T., Feng, B., Heidet, F., Hu, R.

    Published in EPJ Web of conferences (01-01-2021)
    “…In recent years, there has been renewed interest in Molten Salter Reactors (MSRs) for their potential advantages compared to reactors that rely on solid fuel…”
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    Impact of minor actinide recycling on sustainable fuel cycle options by Heidet, F., Kim, T.K., Taiwo, T.A.

    Published in Nuclear engineering and design (01-11-2017)
    “…•Impact of recycling minor actinides in advanced fuel cycles is assessed.•Analysis performed for systems containing a fast system or a fast and a thermal…”
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    Journal Article
  7. 7

    Core design and performance of the FASt TEst reactor (FASTER) by Heidet, F., Grandy, C., Hill, R.N.

    Published in Progress in nuclear energy (New series) (01-09-2018)
    “…The core design and performance of the FASt TEst reactor (FASTER) is presented. The FASTER core design is not based on any previously existing fast reactor,…”
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  8. 8

    ADVANCED MANUFACTURING FOR NUCLEAR CORE DESIGN by Betzler, B. R., Ade, B. J., Wysocki, A. J., Greenwood, M. S., Heineman, J. J. W., Chesser, P. C., Jain, P. K., Heidet, F., Bergeron, A.

    Published in EPJ Web of conferences (01-01-2021)
    “…Advanced manufacturing has the potential to revitalize US manufacturing, with valuable applications in several industries, including aerospace, automotive, and…”
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  9. 9

    Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems by Brown, N.R., Powers, J.J., Feng, B., Heidet, F., Stauff, N.E., Zhang, G., Todosow, M., Worrall, A., Gehin, J.C., Kim, T.K., Taiwo, T.A.

    Published in Nuclear engineering and design (01-08-2015)
    “…•Comparison of intermediate and fast spectrum thorium-fueled reactors.•Variety of reactor technology options enables self-sustaining thorium fuel cycles.•Fuel…”
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    Journal Article
  10. 10

    FASt TEst Reactor (FASTER) design overview by Heidet, F., Grandy, C., Sumner, T., Belch, H., Brunett, A., Hill, R., Hoffman, E., Jin, E., Mohamed, W., Moisseytsev, A., Passerini, S., Sienicki, J., Vilim, R., Hayes, S.

    Published in Progress in nuclear energy (New series) (01-09-2018)
    “…As part of the ADTR study, reactor point designs were developed in order to inform the study and assess performance that could be expected from various types…”
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    Journal Article
  11. 11

    Molten salt reactor core simulation with PROTEUS by Fei, T., Feng, B., Heidet, F.

    Published in Annals of nuclear energy (01-06-2020)
    “…•The High-fidelity code PROTEUS was used to simulate a Molten Salt Reactor.•The results (k-eff and flux distribution) from PROTEUS and OpenMC agree well.•The…”
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  12. 12

    Molten salt reactor core simulation with PROTEUS by Fei, T., Feng, B., Heidet, F.

    Published in Annals of nuclear energy (23-10-2019)
    “…The Nuclear Energy Advance Modeling and Simulation Program (NEAMS) of the US Department of Energy (DOE) aims to develop advanced simulation tools to aid the…”
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    Analysis of ZPPR-15 experimental data for VTR software validation by Aliberti, G., Smith, M.A., Zhong, Z., Lell, R.M., Heidet, F.

    Published in Annals of nuclear energy (01-09-2021)
    “…As part of the Versatile Test Reactor (VTR) program, extensive validation work is being performed to demonstrate the fidelity of the Argonne Reactor Code (ARC)…”
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  15. 15

    Impact of minor actinide recycling on sustainable fuel cycle options by Heidet, F, Kim, TK, Taiwo, TA

    Published in Nuclear engineering and design (01-11-2017)
    “…The recent Evaluation and Screening study chartered by the U.S. Department of Energy, Office of Nuclear Energy, has identified four fuel cycle options as being…”
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    Journal Article
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