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  1. 21
    Irradiation behavior of uranium monocarbide. Task No. 6

    Irradiation behavior of uranium monocarbide. Task No. 6 by Chubb, W, Melehan, J B, Markworth, A J, Perrin, J S, Wullaert, R A, Gates, J E

    Published 1967
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  2. 22
    Fission product behavior within two W--UO$sub 2$ cermet fuel elements irradiated in a temperature gradient

    Fission product behavior within two W--UO$sub 2$ cermet fuel elements irradiated in a temperature gradient

    Published 1968
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  3. 23
    ¹²⁹I release fractions in unsaturated tests with fast-flux MOX fuels.

    ¹²⁹I release fractions in unsaturated tests with fast-flux MOX fuels.

    Published 2000
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  4. 24
    POPDOSE-SR A Routine Release Atmospheric Population Dose Model Used at SRS.

    POPDOSE-SR A Routine Release Atmospheric Population Dose Model Used at SRS.

    Published 2001
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  5. 25
    The Phebus FP thermal-hydraulic analysis with Melcor

    The Phebus FP thermal-hydraulic analysis with Melcor

    Published 1995
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  6. 26
    Experience with ALARA and ALARA procedures in a nuclear power plant

    Experience with ALARA and ALARA procedures in a nuclear power plant

    Published 1995
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  7. 27
    Coupled calculation of the radiological release and the thermal-hydraulic behavior of a 3-loop PWR after a SGTR by means of the code RELAP5

    Coupled calculation of the radiological release and the thermal-hydraulic behavior of a 3-loop PWR after a SGTR by means of the code RELAP5

    Published 1995
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  8. 28
    NAUAHYGROS - A code for calculating aerosol behavior in nuclear power plant containments following a severe accident

    NAUAHYGROS - A code for calculating aerosol behavior in nuclear power plant containments following a severe accident

    Published 1995
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  9. 29
    HTGR fuels and core development program. Quarterly progress report for the period ending May 31, 1976. [Graphite and fuels irradiation; fission product release]

    HTGR fuels and core development program. Quarterly progress report for the period ending May 31, 1976. [Graphite and fuels irradiation; fission product release]

    Published 1976
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  10. 30
    Migration of fission products in UO{sub 2}. Final report

    Migration of fission products in UO{sub 2}. Final report

    Published 1995
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  11. 31
    Proceedings of the 23rd DOE/NRC nuclear air cleaning conference

    Proceedings of the 23rd DOE/NRC nuclear air cleaning conference

    Published 1995
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  12. 32
    Fission product release from core-concrete mixtures

    Fission product release from core-concrete mixtures

    Published 1988
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  13. 33
    Local fault tolerance of metal fuel

    Local fault tolerance of metal fuel

    Published 1986
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  14. 34
    Direct electrical heating of irradiated EBR-II Mark-II driver fuel

    Direct electrical heating of irradiated EBR-II Mark-II driver fuel

    Published 1985
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  15. 35
    Release of adsorbed krypton and xenon from spilled charcoal

    Release of adsorbed krypton and xenon from spilled charcoal

    Published 1976
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  16. 36
    Semi-empirical model for radioactive fission gas release from UO/sub 2/

    Semi-empirical model for radioactive fission gas release from UO/sub 2/

    Published 1976
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  17. 37
    Performance of metallic fuels in liquid-metal fast reactors

    Performance of metallic fuels in liquid-metal fast reactors

    Published 1984
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  18. 38
    Recent plant studies using Victoria 2.0

    Recent plant studies using Victoria 2.0

    Published 2000
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  19. 39
    Corrosion Tests of LWR Fuels - Nuclide Release

    Corrosion Tests of LWR Fuels - Nuclide Release

    Published 2001
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  20. 40
    Examination of T-111 clad uranium nitride fuel pins irradiated up to 13,000 hours at a clad temperature of 990°C

    Examination of T-111 clad uranium nitride fuel pins irradiated up to 13,000 hours at a clad temperature of 990°C

    Published 1973
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