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Advanced BWR core component designs and the implications for SFD analysis CONF-970824-2 DE97 002970

Advanced BWR core component designs and the implications for SFD analysis CONF-970824-2 DE97 002970
PaperMicroform規格・テクニカルリポート類
Ott, L. J1997<LS-DE97/002970>
National Diet LibraryOther Libraries in Japan

In-vessel core degradation code validation matrix (NEA ; NEA-CSNI-R-95-21; DE98617538)

In-vessel core degradation code validation matrix (NEA ; NEA-CSNI-R-95-21; DE98617538)
Paper図書
Haste, T.J., Adroguer, B., Gauntt, R.O. [et al.]Nuclear Energy Agency, 751996.12.31.
Other Libraries in Japan
  • Author HeadingHaste, T.J. Adroguer, B. Gauntt, R.O. Martinez, J.A. Ott, L.J. Sugimoto, J. Trambauer, K.

INTERPRETATION OF THE RESULTS OF THE CORA-33 DRY CORE BWR TEST (CONF ; CONF-931079-6)

INTERPRETATION OF THE RESULTS OF THE CORA-33 DRY CORE BWR TEST (CONF ; CONF-931079-6)
Paper図書
OTT, L.J.// HAGEN, S. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1993.
Other Libraries in Japan
  • Author HeadingOTT, L.J. HAGEN, S.

BWR CORE MELT PROGRESSION PHENOMENA: EXPERIMENTAL ANALYSES (CONF ; CONF-9205164-1)

BWR CORE MELT PROGRESSION PHENOMENA: EXPERIMENTAL ANALYSES (CONF ; CONF-9205164-1)
Paper図書
OTT, L.J. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1992.
Other Libraries in Japan
  • Author HeadingOTT, L.J.

IN-VESSEL PHENOMENA - CORA (CONF ; CONF-9105173-3-EXTD.ABST.)

IN-VESSEL PHENOMENA - CORA (CONF ; CONF-9105173-3-EXTD.ABST.)
Paper図書
OTT, L.J.// VAN RIJ, W.I. (OAK RIDGE NATIONAL LAB., TN (USA))1991.
Other Libraries in Japan
  • Author HeadingOTT, L.J. VAN RIJ, W.I.

EXPERIMENT-SPECIFIC ANALYSES IN SUPPORT OF CODE DEVELOPMENT (CONF ; CONF-901085-6)

EXPERIMENT-SPECIFIC ANALYSES IN SUPPORT OF CODE DEVELOPMENT (CONF ; CONF-901085-6)
Paper図書
OTT, L.J. (OAK RIDGE NATIONAL LAB., TN (USA))1990.
Other Libraries in Japan
  • Author HeadingOTT, L.J.

BWR LOWER PLENUM DEBRIS BED MODELS FOR MELCOR (CONF ; CONF-911079-1)

BWR LOWER PLENUM DEBRIS BED MODELS FOR MELCOR (CONF ; CONF-911079-1)
Paper図書
HODGE, S.A.// OTT, L.J. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1991.
Other Libraries in Japan
  • Author HeadingHODGE, S.A. OTT, L.J.

(INSTALLATION OF A BOILING WATER REACTOR CORE MELT PROGRESSION PHENOMENA PROGRAM). (ORNL ; ORNL/FTR-3629)

(INSTALLATION OF A BOILING WATER REACTOR CORE MELT PROGRESSION PHENOMENA PROGRAM). (ORNL ; ORNL/FTR-3629)
Paper図書
OTT, L.J.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1990.
Other Libraries in Japan
  • Author HeadingOTT, L.J.

(BOILING WATER REACTOR (BWR) CORA EXPERIMENTS). (ORNL ; ORNL/FTR-3780)

(BOILING WATER REACTOR (BWR) CORA EXPERIMENTS). (ORNL ; ORNL/FTR-3780)
Paper図書
OTT, L.J.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1990.
Other Libraries in Japan
  • Author HeadingOTT, L.J.

(SEVERE ACCIDENT TECHNOLOGY OF BWR (BOILING WATER REACTOR) REACTORS). (ORNL ; ORNL/FTR-3427)

(SEVERE ACCIDENT TECHNOLOGY OF BWR (BOILING WATER REACTOR) REACTORS). (ORNL ; ORNL/FTR-3427)
Paper図書
OTT, L.J.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1989.
Other Libraries in Japan
  • Author HeadingOTT, L.J.

STATION BLACKOUT CALCULATIONS FOR BROWNS FERRY. (CONF ; CONF-8510173-29)

STATION BLACKOUT CALCULATIONS FOR BROWNS FERRY. (CONF ; CONF-8510173-29)
Paper図書
OTT, L.J.(et al.)1985.
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  • Author HeadingOTT, L.J.

Effect of small-capacity, high-pressure injection systems on TQUV sequences at Browns Ferry Unit One (ORNL/TM ; ORNL/TM-8635)

Effect of small-capacity, high-pressure injection systems on TQUV sequences at Browns Ferry Unit One (ORNL/TM ; ORNL/TM-8635)
Paper図書
Oak Ridge National Lab., TN (USA)(Oak Ridge National Lab., TN (USA))1983.
Other Libraries in Japan
  • Author HeadingHarrington, R.M. Ott, L.J.

PRELIMINARY FLASHING MULTIPHASE FLOW ANALYSIS WITH APPLICATION TO LETDOWN VALVES IN COAL-CONVERSION PROCESSES. (ORNL ; ORNL-TM-8160)

PRELIMINARY FLASHING MULTIPHASE FLOW ANALYSIS WITH APPLICATION TO LETDOWN VALVES IN COAL-CONVERSION PROCESSES. (ORNL ; ORNL-TM-8160)
Paper図書
OTT, L.J.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1982.
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  • Author HeadingOTT, L.J.

THERMAL-HYDRAULIC TEST FACILITY BUNDLE 3 IN-CORE INSTRUMENTATION AND OPERATING HISTORY. (NUREG ; NUREG-CR-2609)

THERMAL-HYDRAULIC TEST FACILITY BUNDLE 3 IN-CORE INSTRUMENTATION AND OPERATING HISTORY. (NUREG ; NUREG-CR-2609)
Paper図書
OTT, L.J.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1982.
Other Libraries in Japan
  • Author HeadingOTT, L.J.

Quarterly Progress Report on Blowdown Heat Transfer Separate-Effects Program for October-December 1980 (NUREG ; NUREG/CR-2020; ORNL-NUREG-TM-449)

Quarterly Progress Report on Blowdown Heat Transfer Separate-Effects Program for October-December 1980 (NUREG ; NUREG/CR-2020; ORNL-NUREG-TM-449)
Paper図書
Craddick, W.G./Ott, L.J./and othersNUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1981.
Other Libraries in Japan
  • Author HeadingCraddick, W.G. Ott, L.J. and others

Quarterly Progress Report on Blowdown Heat Transfer Separate-Effects Program for January-March 1981 (NUREG ; NUREG/CR-2170/VOL.1; ORNL/TM-7846)

Quarterly Progress Report on Blowdown Heat Transfer Separate-Effects Program for January-March 1981 (NUREG ; NUREG/CR-2170/VOL.1; ORNL/TM-7846)
Paper図書
Craddick, W.G./Ott, L.J./and othersNUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1981.
Other Libraries in Japan
  • Author HeadingCraddick, W.G. Ott, L.J. and others

Thermocouple Signal Sensitivity to the Sheath Thickness of Thermal-Hydraulic Test Facility Indirectly Heated Electric Fuel Pin Simulators (NUREG ; NUREG/CR-1347; ORNL/NUREG-62)

Thermocouple Signal Sensitivity to the Sheath Thickness of Thermal-Hydraulic Test Facility Indirectly Heated Electric Fuel Pin Simulators (NUREG ; NUREG/CR-1347; ORNL/NUREG-62)
Paper図書
Dabbs, R.D./Ott, L.J.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1980.
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  • Author HeadingDabbs, R.D. Ott, L.J.

ORTCAL: a code for THTF heater rod thermocouple calibration (NUREG ; NUREG/CR-0342) (Hedrick, R.A.)

ORTCAL: a code for THTF heater rod thermocouple calibration (NUREG ; NUREG/CR-0342) (Hedrick, R.A.)
Paper図書
Ott, L.J., Hedrick, R.A.Oak Ridge National Lab.1979.2.
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  • Author HeadingOtt, L.J.

ORTCAL ; A Code for THTF Heater Rod Thermocouple Calibration (NUREG ; NUREG/CR-0342; ORNL/NUREG-51)

ORTCAL ; A Code for THTF Heater Rod Thermocouple Calibration (NUREG ; NUREG/CR-0342; ORNL/NUREG-51)
Paper図書
Ott, L.J./Hedrick, R.A.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1979.
Other Libraries in Japan
  • Author HeadingOtt, L.J. Hedrick, R.A.

Surface Heat Flux Perturbations in BDHT Fuel Pin Simulators. (NUREG ; NUREG/CR-0610; ORNL/NUREG-54)

Surface Heat Flux Perturbations in BDHT Fuel Pin Simulators. (NUREG ; NUREG/CR-0610; ORNL/NUREG-54)
Paper図書
Ott, L.J./Childs, K.W.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1979.
Other Libraries in Japan
  • Author HeadingOtt, L.J. Childs, K.W.
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