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  1. 281
    FTR power-to-melt study. Phase I. Evaluation of deterministic models

    FTR power-to-melt study. Phase I. Evaluation of deterministic models

    Published 1978
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  2. 282
    Determination of end-of-life-failure fractions of HTGR-fuel particles by postirradiation annealing and beta autoradiography

    Determination of end-of-life-failure fractions of HTGR-fuel particles by postirradiation annealing and beta autoradiography

    Published 1978
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  3. 283
    Fission product inventory, release fractions, and radiation levels from fission products released to the test chamber

    Fission product inventory, release fractions, and radiation levels from fission products released to the test chamber

    Published 1978
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  4. 284
    Fission-gas bubble modeling for LMFBR accidents

    Fission-gas bubble modeling for LMFBR accidents

    Published 1977
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  5. 285
    Determination of defective particle fraction in HTGR fuels

    Determination of defective particle fraction in HTGR fuels

    Published 1976
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  6. 286
    TRIGA high wt -% LEU fuel development program. Final report

    TRIGA high wt -% LEU fuel development program. Final report

    Published 1980
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  7. 287
    Quarterly progress report on fission product release from LWR fuel, October--December 1976

    Quarterly progress report on fission product release from LWR fuel, October--December 1976

    Published 1976
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  8. 288
    HTGR Fuels and Core Development Program. Quarterly progress report for the period ending August 31, 1977. [Graphite and fuel irradiation; fission product release]

    HTGR Fuels and Core Development Program. Quarterly progress report for the period ending August 31, 1977. [Graphite and fuel irradiation; fission product release]

    Published 1977
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  9. 289
    Liquid-metal fast-breeder-reactor program reference fuel studies. Eighth quarterly report, August-October 1976. [LMFBR]

    Liquid-metal fast-breeder-reactor program reference fuel studies. Eighth quarterly report, August-October 1976. [LMFBR]

    Published 1976
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  10. 290
    Risk-based fault tree analysis method for identification, preliminary evaluation, and screening of potential accidental release sequences in nuclear fuel cycle operations

    Risk-based fault tree analysis method for identification, preliminary evaluation, and screening of potential accidental release sequences in nuclear fuel cycle operations

    Published 1976
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  11. 291
    Model to predict swelling, gas release, and densification in oxide fuels (AWBA development program)

    Model to predict swelling, gas release, and densification in oxide fuels (AWBA development program)

    Published 1978
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  12. 292
    Fission gas release (FGASRL). [BWR; PWR]

    Fission gas release (FGASRL). [BWR; PWR]

    Published 1978
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  13. 293
    Analysis of fission product behavior in the Saclay Spitfire Loop Test SSL-1. [HTGR]

    Analysis of fission product behavior in the Saclay Spitfire Loop Test SSL-1. [HTGR]

    Published 1978
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  14. 294
    Fission gas release from ThO₂ and ThO₂--UO₂ fuels (LWBR development program)

    Fission gas release from ThO₂ and ThO₂--UO₂ fuels (LWBR development program)

    Published 1978
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  15. 295
    Gas-Cooled Fast Reactor Program. Progress report, July 1, 1975--December 31, 1976

    Gas-Cooled Fast Reactor Program. Progress report, July 1, 1975--December 31, 1976

    Published 1977
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  16. 296
    Transport and deposition of airborne fission products in containment systems of water cooled reactors following postulated accidents

    Transport and deposition of airborne fission products in containment systems of water cooled reactors following postulated accidents

    Published 1974
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  17. 297
    Savannah River Site K-Reactor Probabilistic Safety Assessment

    Savannah River Site K-Reactor Probabilistic Safety Assessment

    Published 1992
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  18. 298
    Code manual for CONTAIN 2.0 A computer code for nuclear reactor containment analysis.

    Code manual for CONTAIN 2.0 A computer code for nuclear reactor containment analysis.

    Published 1997
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  19. 299
    FRAPCON-3 Modifications to fuel rod material properties and performance models for high-burnup application.

    FRAPCON-3 Modifications to fuel rod material properties and performance models for high-burnup application.

    Published 1997
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  20. 300
    Radiation levels from fission products released to the pressure suppression tank

    Radiation levels from fission products released to the pressure suppression tank

    Published 1978
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