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Volumn 197, Issue 3, 2000, Pages 281-299

Hydrogen management and overpressure protection of the containment for future boiling water reactors

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; CONTAINMENT VESSELS; CORE MELTDOWN; DECOMPOSITION; FALLOUT; HYDROGEN; OXYGEN; PALLADIUM; PROBABILITY; RISK ASSESSMENT; TANTALUM; WATER;

EID: 0033900576     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(99)00291-5     Document Type: Article
Times cited : (9)

References (33)
  • 4
    • 85031608702 scopus 로고    scopus 로고
    • Devices for the removal of hydrogen
    • Buenos Aires
    • Brockerhoff, P. et al., 1998. Devices for the removal of hydrogen, 12th Hydrogen Conference, Buenos Aires.
    • (1998) 12th Hydrogen Conference
    • Brockerhoff, P.1
  • 5
    • 0027109031 scopus 로고
    • Measurement of diffusive and surface transport resistances for deuterium in palladium-coated zirconium membranes
    • Buxbaum, R.E. et al., 1992. Measurement of diffusive and surface transport resistances for deuterium in palladium-coated zirconium membranes, J. Nucl. Mater., 189.
    • (1992) J. Nucl. Mater. , pp. 189
    • Buxbaum, R.E.1
  • 7
    • 0000354093 scopus 로고
    • Significance of liquid-film coefficients in gas absorption
    • Danckwerts, 1951. Significance of liquid-film coefficients in gas absorption, Ind. Eng. Chem. 43, 6.
    • (1951) Ind. Eng. Chem. , vol.43 , pp. 6
    • Danckwerts1
  • 10
    • 0343330171 scopus 로고
    • High-temperature leak characteristics of PCV hatch flange gasket
    • Hirao, K. et al., 1993. High-temperature leak characteristics of PCV hatch flange gasket. Nucl. Eng. Des. 145.
    • (1993) Nucl. Eng. Des. , pp. 145
    • Hirao, K.1
  • 12
    • 0003994739 scopus 로고
    • Basic safety principles for nuclear power plants
    • IAEA
    • IAEA, 1988. Basic safety principles for nuclear power plants, IAEA Safety Series No. 75-INSAG-3.
    • (1988) IAEA Safety Series No. 75-INSAG-3
  • 16
    • 85010626478 scopus 로고    scopus 로고
    • Fuel-coolant-interaction tests using UO2 corium under ex-vessel conditions
    • Kato, M. et al., 1998. Fuel-coolant-interaction tests using UO2 corium under ex-vessel conditions, Transactions of 1998 Winter Meeting of ANS.
    • (1998) Transactions of 1998 Winter Meeting of ANS
    • Kato, M.1
  • 19
    • 85031611989 scopus 로고    scopus 로고
    • NUPEC, INS/M97-33
    • NUPEC, 1997. INS/M97-33.
    • (1997)
  • 20
    • 85031607768 scopus 로고    scopus 로고
    • Private communication with NUPEC
    • Nagasaka, H., 1999. Private communication with NUPEC.
    • (1999)
    • Nagasaka, H.1
  • 22
    • 0342895118 scopus 로고
    • ABWR evolution program
    • Omoto, A. et al., 1993. ABWR evolution program, Nucl. Eng. Des. 144.
    • (1993) Nucl. Eng. Des. , pp. 144
    • Omoto, A.1
  • 24
    • 85031604275 scopus 로고    scopus 로고
    • A structured and risk-oriented approach for the consideration of severe accidents in the design of containments for future LWRs
    • (submitted for publication)
    • Omoto, A. et al., 1999. A structured and risk-oriented approach for the consideration of severe accidents in the design of containments for future LWRs. Reliability Eng. Syst. Safety (submitted for publication).
    • (1999) Reliability Eng. Syst. Safety
    • Omoto, A.1
  • 25
    • 0021538557 scopus 로고
    • Generation of hydrogen and oxygen by radiolytic decomposition of water in some BWR'
    • Parczewski, K.I. et al., 1984. Generation of hydrogen and oxygen by radiolytic decomposition of water in some BWR', Joint ANS/ASME Conference.
    • (1984) Joint ANS/ASME Conference
    • Parczewski, K.I.1
  • 28
    • 0343330161 scopus 로고
    • ACE Program Phase D: Melt Attack and Coolability Experiments (MACE) Program
    • Seghal, B. et al., 1992. ACE Program Phase D: Melt Attack and Coolability Experiments (MACE) Program, presentation to USNRC, CSARP Meeting.
    • (1992) Presentation to USNRC, CSARP Meeting
    • Seghal, B.1
  • 31
    • 85031608135 scopus 로고    scopus 로고
    • USNRC. 10 CTR 50.34 (f)(2)(ix) and (f)(3)(v)
    • USNRC. 10 CTR 50.34 (f)(2)(ix) and (f)(3)(v).
  • 32
    • 85031608373 scopus 로고    scopus 로고
    • Control of combustible gas concentration in containment following a loss-of-coolant accident
    • USNRC.
    • USNRC. Control of combustible gas concentration in containment following a loss-of-coolant accident. Regulatory Guide 1.7.
    • Regulatory Guide 1.7
  • 33
    • 85031608690 scopus 로고    scopus 로고
    • private communication with Watanabe, TSI
    • Watanabe, private communication with Watanabe, TSI.
    • Watanabe1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.