메뉴 건너뛰기




Volumn 36, Issue 11, 1999, Pages 1076-1088

Development of severe accident analysis code SAMPSON in IMPACT project

Author keywords

Candling; Computer codes; Computerized simulation; Crust forming; Ex vessel phenomena; In vessel retention; Mechanistic model; Melting; Molten debris cooling; Nuclear fuels; Parallel processing; Reactor accidents; Reactor safety; Simulation code; System analysis

Indexed keywords

ACCIDENT PREVENTION; COMPUTER SIMULATION; COMPUTER SOFTWARE; LOSS OF COOLANT ACCIDENTS; MELTING; NUCLEAR FUELS; PARALLEL PROCESSING SYSTEMS; PRESSURE VESSELS;

EID: 0033349687     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.1999.9726300     Document Type: Article
Times cited : (71)

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


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.