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  1. 6941
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    Technical feasibility and reliability of passive safety systems for nuclear power plants: proceedings.

    Published 1996.
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  2. 6942
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    Behaviour of LWR [Ligth Water Reactor] core materials under accident conditions: proceedings.

    Published 1996.
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  3. 6943
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    Engineering safety of nuclear fuel cycle facility.

    Published 1996.
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  4. 6944
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    Nuclear data: proceedings. by Iguchi, Tetsuo

    Published 1996.
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  5. 6945
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    Nuclear criticality safety handbook.

    Published 1995.
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  6. 6946
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    Annual report of the Osaka Laboratory for Radiation Chemistry of Japan Atomic Energy Research Institute. [No.28], [April 1, 1994 - March 31, 1995].

    Published 1995.
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  7. 6947
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    Noise thermometer. by Brixy, Heintz Von

    Published 1996.
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  8. 6948
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    Feasibility study of steady state magnetic field measurement. by Kawahata, Kazuo

    Published 1995.
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  9. 6949
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    Trasient thermal and stress analyses of the ITER [International Thermonuclear Experimental Reactor] shielding blanket/first wall under off-normal conditions. by Furuya, Kazuyuki

    Published 1995.
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  10. 6950
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    CORCON-Mod3 analysis of SURC experiments on molten core concrete interaction. by Yan, Jinquan

    Published 1995.
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  11. 6951
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    Preirradiation characterization of HTGR [High-Temperature Gas-Cooled Reactors] fuel for HRB-22 capsule irradiation test. [JAERI / USDOE collaborative irradiation test for HTGR fuel... by Minato, Kazuo

    Published 1996.
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  12. 6952
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    Irradiation tests of critical components for remote handling system in gamma radiation environment. by Obara, Kenjiro

    Published 1996.
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  13. 6953
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    Manual for troubleshooting and upgrading of neutron generators.

    Published 1996.
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  14. 6954
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    Antibodies immobilized on magnetic particles for radioimmunoassay and immunoradiometric assay of hormones.

    Published 1996.
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  15. 6955
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    Advanced fuels with reduced actinide generation.

    Published 1996.
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  16. 6956
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    Potential for nuclear desalination as a source of low cost potable water in North Africa.

    Published 1996.
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  17. 6957
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    HTGR [High Temperature Gas Cooled and Graphite Moderated Reactors] technologies: proceedings.

    Published 1996.
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  18. 6958
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    Behavior of irradiated PWR [Presssurized Water Reactor] fuel under a simulated RIA [Reactivity Initiated Accident] condition: [results of NSRR [Nuclear Safety Research Reactor] tes... by Sasajima, Hideo

    Published 1995.
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  19. 6959
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    Oxidation characteristics of oxide dispersion strengthened [ODS] alloy. by Suzuki, Tomio

    Published 1996.
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  20. 6960
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    Numerical prediction of turbulent heat transfer augmentation in an annular fuel channel with two-dimensional square ribs. by Takase, Kazuyuki

    Published 1996.
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