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1
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0003198445
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The “IMPACT super-simulation” project for exploring NPP fundamental phenomena
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Espoo, Finland, Sep
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Ujita, H., et al.: The “IMPACT super-simulation” project for exploring NPP fundamental phenomena, Second CSNI Specialist Meeting on Simulators and Plant Analysers, Espoo, Finland, Sep., 1997.
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Second CSNI Specialist Meeting on Simulators and Plant Analysers
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Ujita, H.1
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2
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0003263591
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Development of the simulation system “IMPACT” for analysis of NPP severe accidents
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Kyoto, Japan, Sep
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Naitoh, M., et al.: Development of the simulation system “IMPACT” for analysis of NPP severe accidents, NURETH8, Kyoto, Japan, Sep., 1997.
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(1997)
NURETH8
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Naitoh, M.1
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3
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2142763412
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Basic models and verification study on fuel rod heat-up and fission product release analysis modules in SAMPSON for the IMPACT project
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Tokyo, Apr
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Morii, T., et al.: Basic models and verification study on fuel rod heat-up and fission product release analysis modules in SAMPSON for the IMPACT project, 7th Int. Conf. on Nuclear Engineering, Tokyo, Apr. 1999.
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7Th Int. Conf. On Nuclear Engineering
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Morii, T.1
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4
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85010578657
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Development of molten core relocation analysis module MCRA in the severe accident analysis code SAMPSON, Submitted to
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Satoh, N., et al.: Development of molten core relocation analysis module MCRA in the severe accident analysis code SAMPSON, Submitted to J. Nucl. Sci. Technol.
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J. Nucl. Sci. Technol
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Satoh, N.1
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5
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0033327781
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Development of debris coolability analysis module in severe accident analysis code SAMPSON for IMPACT project
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Ujita, H., et al.: Development of debris coolability analysis module in severe accident analysis code SAMPSON for IMPACT project, J. Nucl. Sci. Technol., 36[10], 940 (1999).
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Ujita, H.1
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6
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85010598747
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Development of the VESUVIUS code for steam explosion analysis Part 1; Molten jet breakup modeling
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Vierow, K., et al: Development of the VESUVIUS code for steam explosion analysis Part 1; Molten jet breakup modeling, J. Jpn. Soc. Multiphase Flow, 12 [3], 242 (1998).
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J. Jpn. Soc. Multiphase Flow
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Vierow, K.1
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8
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0343644205
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Boiling transition analysis code for LWR fuel bundles in the IMPACT project
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San Francisco, CA, USA
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Naitoh, M., et al.: Boiling transition analysis code for LWR fuel bundles in the IMPACT project, Proc. NURETH-9, San Francisco, CA, USA, (1999).
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Proc. NURETH-9
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Naitoh, M.1
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9
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0342773963
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Boiling transition analysis code of the IMPACT project
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Washington, Nov
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Iwashita, T., et al.: Boiling transition analysis code of the IMPACT project, ANS 1998 Winter Mtg., Washington, Nov. 1998.
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(1998)
ANS 1998 Winter Mtg
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Iwashita, T.1
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10
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0343208623
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Development of fluid-structure interaction analysis code in the IMPACT project
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Washington, Nov
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Ando, Y., et al.: Development of fluid-structure interaction analysis code in the IMPACT project, ANS 1998 Winter Mtg., Washington, Nov. 1998.
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(1998)
ANS 1998 Winter Mtg
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Ando, Y.1
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11
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0032245138
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Development of LGA & LBE 2D parallel programs
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Ujita, H., et al.: Development of LGA & LBE 2D parallel programs, Int. J. Math. Phys. C, Phys. Comput., 9[8], 1203-1220 (1998).
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Int. J. Math. Phys. C, Phys. Comput.
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Ujita, H.1
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13
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85010572093
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A computer code for severe nuclear reactor accident containment analysis
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User’s manual for CONTAIN 1.1: A computer code for severe nuclear reactor accident containment analysis, NUREG/CR-5026 (5AND87-2309), (1987).
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(1987)
NUREG/CR-5026 (5AND87-2309)
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14
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0003737834
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VICTORIA; A mechanistic model of radionuclide behavior in the reactor coolant system under severe accident conditions
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Heames, T. J., et al.: VICTORIA; A mechanistic model of radionuclide behavior in the reactor coolant system under severe accident conditions, NUREG/CR-5545 Rev. 1 (SAND90-0756), (1992).
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(1992)
NUREG/CR-5545 Rev. 1 (SAND90-0756)
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Heames, T.J.1
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15
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0342773954
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Development of the aerosol behavior code MACRES and study of its dependency on thermal-hydraulic conditions
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Thermohydraulics of Containment and Severe Accidents, Pisa, Italy
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Akagane, K., et al.: Development of the aerosol behavior code MACRES and study of its dependency on thermal-hydraulic conditions, Proc. Int. Conf, on New Trends in Nuclear System Thermohydraulics. Vol. 2, Thermohydraulics of Containment and Severe Accidents, Pisa, Italy, (1993).
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Proc. Int. Conf, on New Trends in Nuclear System Thermohydraulics
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Akagane, K.1
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