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SYSTEM MODEL DEVELOPMENT FOR NUCLEAR THERMAL PROPULSION (CONF ; CONF-9208154-1)

SYSTEM MODEL DEVELOPMENT FOR NUCLEAR THERMAL PROPULSION (CONF ; CONF-9208154-1)
紙図書
HANNAN, N.A.// WORLEY, B.A.// WALTON, J.T.// PERKINS, K.R.// BUKSA, J.J.// DOBRANICH, D. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1992.
全国の図書館
  • 著者標目HANNAN, N.A. WORLEY, B.A. WALTON, J.T. PERKINS, K.R. BUKSA, J.J. DOBRANICH, D.

SYSTEM MODEL DEVELOPMENT FOR NUCLEAR THERMAL PROPULSION (SAND ; SAND-92-1820C)

SYSTEM MODEL DEVELOPMENT FOR NUCLEAR THERMAL PROPULSION (SAND ; SAND-92-1820C)
紙図書
WALTON, J.T.// HANNAN, N.A.// PERKINS, K.R.// BUKSA, J.J.// WORLEY, B.A.// DOBRANICH, D. (SANDIA NATIONAL LABS., ALBUQUERQUE, NM (UNITED STATES))Sandia National Laboratories(Sandia National Laboratories)1992.
全国の図書館
  • 著者標目WALTON, J.T. HANNAN, N.A. PERKINS, K.R. BUKSA, J.J. WORLEY, B.A. DOBR...

ASSESSMENT OF SEVERE ACCIDENT PREVENTION AND MITIGATION FEATURES: PWR, LARGE DRY CONTAINMENT DESIGN. (NUREG ; NUREG-CR-4920-VOL.4)

ASSESSMENT OF SEVERE ACCIDENT PREVENTION AND MITIGATION FEATURES: PWR, LARGE DRY CONTAINMENT DESIGN. (NUREG ; NUREG-CR-4920-VOL.4)
紙図書
PERKINS, K.R.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1988.
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  • 著者標目PERKINS, K.R.

SEVERE ACCIDENTS IN SPENT FUEL POOLS IN SUPPORT OF GENERIC SAFETY ISSUE 82 (NUREG ; NUREG/CR-4982; BNL-NUREG-52093)

SEVERE ACCIDENTS IN SPENT FUEL POOLS IN SUPPORT OF GENERIC SAFETY ISSUE 82 (NUREG ; NUREG/CR-4982; BNL-NUREG-52093)
紙図書
SAILOR, V.L./PERKINS, K.R./and othersNUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
全国の図書館
  • 著者標目SAILOR, V.L. PERKINS, K.R. and others

Severe accidents in spent fuel pools in support of generic safety, Issue 82 (BNL-NUREG ; BNL-NUREG-52093)

Severe accidents in spent fuel pools in support of generic safety, Issue 82 (BNL-NUREG ; BNL-NUREG-52093)
紙図書
Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor and Plant Systems(Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor and Plant Systems)1987.
全国の図書館
  • 著者標目Connell, H.R. Perkins, K.R. Sailor, V.L. Weeks, J.R.

CONTAINMENT PERFORMANCE FOR THE CORE MELT ACCIDENTS IN BWRS WITH MARK I AND MARK II CONTAINMENTS. (BNL ; BNL-NUREG-37676)

CONTAINMENT PERFORMANCE FOR THE CORE MELT ACCIDENTS IN BWRS WITH MARK I AND MARK II CONTAINMENTS. (BNL ; BNL-NUREG-37676)
紙図書
PERKINS, K.R.(et al.)Brookhaven National Laboratory(Brookhaven National Laboratory)1985.
全国の図書館
  • 著者標目PERKINS, K.R.

BORON INJECTION AT NATURAL CIRCULATION CONDITIONS IN PWRS. (BNL ; BNL-NUREG-33897)

BORON INJECTION AT NATURAL CIRCULATION CONDITIONS IN PWRS. (BNL ; BNL-NUREG-33897)
紙図書
PERKINS, K.R.Brookhaven National Laboratory(Brookhaven National Laboratory)1983.
全国の図書館
  • 著者標目PERKINS, K.R.

BORON INJECTION AT NATURAL CIRCULATION CONDITIONS IN PWRS (CONF ; CONF-830901-22)

BORON INJECTION AT NATURAL CIRCULATION CONDITIONS IN PWRS (CONF ; CONF-830901-22)
紙図書
1983.
全国の図書館

CONTAINMENT PERFORMANCE FOR THE CORE MELT ACCIDENTS IN BWRS WITH MARK I AND MARK II CONTAINMENTS (CONF ; CONF-850206--35)

CONTAINMENT PERFORMANCE FOR THE CORE MELT ACCIDENTS IN BWRS WITH MARK I AND MARK II CONTAINMENTS (CONF ; CONF-850206--35)
紙図書
1985.
全国の図書館
  • 著者標目Perkins, K.R. Yang, J.W. Greene, G.A. Pratt...

IMPACT OF CORE-CONCRETE INTERACTIONS IN THE MARK I CONTAINMENT DRYWELL ON CONTAINMENT INTEGRITY AND FAILURE OF THE DRYWELL LINER (CONF ; CONF-851019--8)

IMPACT OF CORE-CONCRETE INTERACTIONS IN THE MARK I CONTAINMENT DRYWELL ON CONTAINMENT INTEGRITY AND FAILURE OF THE DRYWELL LINER (CONF ; CONF-851019--8)
紙図書
1985.
全国の図書館
  • 著者標目Greene, G.A. Perkins, K.R. Hodge, S.A. Brookhaven Nation...

ANALYSIS OF BORON INJECTION TRANSIENTS IN PRESSURIZED WATER REACTORS AT NATURAL CIRCULATION CONDITIONS. (BNL ; BNL-NUREG-28972)

ANALYSIS OF BORON INJECTION TRANSIENTS IN PRESSURIZED WATER REACTORS AT NATURAL CIRCULATION CONDITIONS. (BNL ; BNL-NUREG-28972)
紙図書
PERKINS, K.R.(et al.)Brookhaven National Laboratory(Brookhaven National Laboratory)1981.
全国の図書館
  • 著者標目PERKINS, K.R.

ANALYSIS OF BORON INJECTION TRANSIENTS IN PRESSURIZED WATER REACTORS AT NATURAL CIRCULATION CONDITIONS (CONF ; CONF-810606-20)

ANALYSIS OF BORON INJECTION TRANSIENTS IN PRESSURIZED WATER REACTORS AT NATURAL CIRCULATION CONDITIONS (CONF ; CONF-810606-20)
紙図書
1981.
全国の図書館

IN-VESSEL NATURAL CIRCULATION DURING A HYPOTHETICAL LOSS-OF-HEAT-SINK ACCIDENT... (BNL ; BNL-NUREG-26131)

IN-VESSEL NATURAL CIRCULATION DURING A HYPOTHETICAL LOSS-OF-HEAT-SINK ACCIDENT... (BNL ; BNL-NUREG-26131)
紙図書
PERKINS, K.R.(et al.)Brookhaven National Laboratory(Brookhaven National Laboratory)1979.
全国の図書館
  • 著者標目PERKINS, K.R.

ANALYSIS OF THE FFTF PRIMARY PIPE RUPTURE TRANSIENTS. (BNL ; BNL-NUREG-25493)

ANALYSIS OF THE FFTF PRIMARY PIPE RUPTURE TRANSIENTS. (BNL ; BNL-NUREG-25493)
紙図書
PERKINS, K.R.(et al.)Brookhaven National Laboratory(Brookhaven National Laboratory)1979.
全国の図書館
  • 著者標目PERKINS, K.R.

REVIEW OF THE FFTF NATURAL CIRCULATION TEST PLANS. (BNL ; BNL-NUREG-24040)

REVIEW OF THE FFTF NATURAL CIRCULATION TEST PLANS. (BNL ; BNL-NUREG-24040)
紙図書
PERKINS, K.R.(et al.)Brookhaven National Laboratory(Brookhaven National Laboratory)1978.
全国の図書館
  • 著者標目PERKINS, K.R.

LUMPED-PARAMETER FUEL ROD MODEL FOR RAPID THERMAL TRANSIENTS. (CONF ; CONF-751101-15)

LUMPED-PARAMETER FUEL ROD MODEL FOR RAPID THERMAL TRANSIENTS. (CONF ; CONF-751101-15)
紙図書
PERKINS, K.R.
全国の図書館
  • 著者標目PERKINS, K.R.

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