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  1. 1
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    Spin Dynamics of the Reentrant Spin Glass Fe{sub 0.7}A1{sub 0.3}

    Published 1997
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  2. 2
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    Substitution of modified 9 Cr-1 Mo steel for austentic stainless steels

    Published 1982
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  3. 3
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    Irradiated dynamic fracture toughness of ASTM A533, Grade B, Class 1 steel plate and submerged arc weldment. Heavy section steel technology program technical report No. 41. [Neutro...

    Published 1976
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  4. 4
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    Survey of matrix materials for solidified radioactive high-level waste

    Published 1981
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  5. 5
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    Improved specifications for fast reactor fuel by Powers, H G, Dutt, D S, Schwallie, A L

    Published 1982
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  6. 6
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    Status of Post Irradiation Examination of FCAB and FCAT Irradiation Capsules

    Published 2016
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  7. 7
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    Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys

    Published 2016
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  8. 8
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    Viability of thin wall tube forming of ATF FeCrAl

    Published 2016
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  9. 9
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    Submission of FeCrAl Feedstock for Support of AFC ATR-2 Irradiations

    Published 2016
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  10. 10
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    BISON Fuel Performance Analysis of FeCrAl cladding with updated properties

    Published 2016
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  11. 11
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    Status of FeCrAl ODS Irradiations in the High Flux Isotope Reactor

    Published 2016
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  12. 12
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    DNA Radiation Environments Program Fall 1989 2-meter box experiments and analysis.

    Published 1991
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  13. 13
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    Dimensional changes in FFTF (Fast Flux Test Facility) austenitic cladding and ducts

    Published 1990
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  14. 14
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    New approaches in the USA for high-temperature gas-cooled reactors. Gas-Cooled Reactor Programs

    Published 1985
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  15. 15
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    Monte Carlo and discrete ordinates calculations for 14-MeV neutrons streaming through a stainless steel duct comparisons with Experiment II.

    Published 1985
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  16. 16
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    Performance of titanium stabilized D9 cladding and ducts

    Published 1986
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  17. 17
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    Demonstration of a high burnup heterogeneous core using ferritic/martensitic materials

    Published 1986
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  18. 18
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    Selection of support structure materials for irradiation experiments in the HFIR (High Flux Isotope Reactor) at temperatures up to 500 degrees C

    Published 1990
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  19. 19
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    Results of the preliminary radiological survey at the former Diamond Magnesium Company site, Luckey, Ohio (DML001)

    Published 1990
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  20. 20
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    Experimental stress analysis and fatigue tests of five 24-in. NPS ANSI Standard B16. 9 tees. [PWR; BWR]

    Published 1985
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