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Studies of waste form and buffer material performance at Japan Atomic Energy research institute.
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Design study of a time-of-flight neutron spectrometer for JT-60U.
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Interaction of molten aluminium cladding with U3 Si2 particles under transient conditions.
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Migration behavior and sorption mechanisms of radionuclides in sedimentary sand stones -influence of particle size and weathering-.
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Wall effect correction for a small cylindrical proportional counters.
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Analysis of the plate-out distribution in the vampyr-I experiments by plain code.
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Measurement of formation cross sections of short-lived nuclei by 14 MeV neutrons -Ru, Pd, Cd, Sn-.
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Test of the scroll pump in the Jaeri fuel cleanup system in the tritium systems test assembly -JFCU scroll pump test and result- -JFCU stand alone tritium test 2-.
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Crystal structure of La2-xBaxCuO4: Effects of Ba substitution and pressure.
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Statistical analyses of variability/reproducibility of environmentally assisted cyclic crack growth rate data utilizing JAERI material performance database [JMPD].
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Analytic cross sections for collisions of H1 H2, He and Li atoms and ions with atoms and molecules. I.
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Experimental and analytical studies of high heat flux components for fusion experimental reactor.
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Proceedings of the workshops on the utilization of electron beams, July 9 and 13, 1992, Bangkok and Jakarta.
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Effect of helium on separation performance of cryogenic distillation column cascade for fusion reactor.
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Assessment of TRAC-PF1/MOD1 and TRAC-PF1/MOD2 codes for thermal-hydraulic behavior in pressure vessel during reflood in SCTF test with an inclined radial power distribution.
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Assessment of TRAC-PF1/MOD1 code for thermal-hydraulic behavior in pressure vessel during reflood in SCTF test with a radial power distribution.
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Development of Bermuda; a radiation transport code system part II. Gamma rays transport codes.
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Material and design considerations for the carbon armored ITER divertor.
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Measurement of formation cross sections of short-lived nuclei by 14 MeV neutrons - Ru, Pd, Cd, Sn.
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Experimental data report for test TS-3 reactivity initiated accident test in the NSRR with pre-irradiated BWR fuel rod.
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Parallelization of MCNP4 code by using simple fortran algorithms.
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Formation of solid particles from aqueous solutions of palladium sulfate and of palladium sulfate-silver sulfate by gamma ray irradiation.
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Critical heat flux for rod bundle under high-pressure boil-off conditions.
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A simplified method to estimate beryllium burn up in breeder blankets of a fusion reactor and its impact on a tritium breeding.