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Corporate performance evalution in bank lending dicisions

Corporate performance evalution in bank lending dicisions
Paper図書
R.H. Berry, R.E. Crum, A. WaringChartered Institute of Management Accountants1993
Other Libraries in Japan
  • Author HeadingBerry, R. H. Crum, R. E. Waring, A. Chartered Institute of Manage...

Estimates of margins in ASME Code strength values for stainless steel nuclear piping INEL-95/00197 DE96 002047 CONF-950740102

Estimates of margins in ASME Code strength values for stainless steel nuclear piping INEL-95/00197 DE96 002047 CONF-950740102
Microform規格・テクニカルリポート類
Ware, A. G1995<LS-DE96/002047>
National Diet Library

Component evaluation for intersystem loss-of-coolant accidents in advanced light water reactors NUREG/CR-6121 TI94 017139

Component evaluation for intersystem loss-of-coolant accidents in advanced light water reactors NUREG/CR-6121 TI94 017139
Microform規格・テクニカルリポート類
Ware, A. G1994<LS-TI94/017139>
National Diet Library

Configuration studies for a small-aspect-ratio tokamak stellarator hybrid ORNL/TM-13252 DE96 014592

Configuration studies for a small-aspect-ratio tokamak stellarator hybrid ORNL/TM-13252 DE96 014592
Microform規格・テクニカルリポート類
Carreras, B. A, Lynch, V. E, Ware, A1996<LS-DE96/014592>
National Diet Library

Application of environmentally-corrected fatigue curves to nuclear power plant components INEL-96/00105 DE96 009012 CONF-96070610

Application of environmentally-corrected fatigue curves to nuclear power plant components INEL-96/00105 DE96 009012 CONF-96070610
Microform規格・テクニカルリポート類
Ware, A. G, Morton, D. K, Nitzel, M. E1996<LS-DE96/009012>
National Diet Library

Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components NUREG/CR-6260 TI95 009088 INEL-95/0045

Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components NUREG/CR-6260 TI95 009088 INEL-95/0045
Microform規格・テクニカルリポート類
Ware, A. G, Morton, D. K, Nitzel, M. E1995<LS-TI95/009088>
National Diet Library

Assessment of pressurized water reactor controlrod drive mechhanism nozzle cracking NUREG/CR-6245 TI95 004202 EGG-2715

Assessment of pressurized water reactor controlrod drive mechhanism nozzle cracking NUREG/CR-6245 TI95 004202 EGG-2715
Microform規格・テクニカルリポート類
Shah, V. N, Ware, A. G, Porter, A. M1994<LS-TI95/004202>
National Diet Library

Effects on fatigue life of gate valves due to higher torque switch settings during operability testing INEL-95/0557 DE96 004130

Effects on fatigue life of gate valves due to higher torque switch settings during operability testing INEL-95/0557 DE96 004130
Microform規格・テクニカルリポート類
Richins, W. D, Snow, S. D, Miller, G. K, Russell, M. J, Ware, A. G1995<LS-DE96/004130>
National Diet Library

PRELIMINARY RISK ASSESSMENT ASSOCIATED WITH IGSCC OF BWR VESSEL INTERNALS. (INEEL ; INEEL/CON-99-00264; DE00008199)

PRELIMINARY RISK ASSESSMENT ASSOCIATED WITH IGSCC OF BWR VESSEL INTERNALS. (INEEL ; INEEL/CON-99-00264; DE00008199)
Paper図書
WARE, A.(et al.)1999.
Other Libraries in Japan

LESSONS LEARNED FROM DROP TESTING. (INEEL ; INEEL/CON-99-00137; DE00007639)

LESSONS LEARNED FROM DROP TESTING. (INEEL ; INEEL/CON-99-00137; DE00007639)
Paper図書
WARE, A.G.(et al.)1999.
Other Libraries in Japan

ASSESSMENT OF FIELD EXPERIENCE RELATED TO PRESSURIZED WATER REACTOR PRIMARY SYSTEM LEAKS. (INEEL ; INEEL/CON-99-00037; DE00009237)

ASSESSMENT OF FIELD EXPERIENCE RELATED TO PRESSURIZED WATER REACTOR PRIMARY SYSTEM LEAKS. (INEEL ; INEEL/CON-99-00037; DE00009237)
Paper図書
WARE, A.G.(et al.)1999.
Other Libraries in Japan

APPLICATION OF NUREG/CR-5999 INTERIM FATIGUE CURVES TO SELECTED NUCLEAR POWER PLANT COMPONENTS. (NUREG ; NUREG/CR-6260)

APPLICATION OF NUREG/CR-5999 INTERIM FATIGUE CURVES TO SELECTED NUCLEAR POWER PLANT COMPONENTS. (NUREG ; NUREG/CR-6260)
Paper図書
WARE, A.G.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1995.
Other Libraries in Japan

Estimates of margins in ASME Code strength values for stainless steel nuclear piping (INEL ; INEL-95/00197; CONF-950740-102; DE96002047)

Estimates of margins in ASME Code strength values for stainless steel nuclear piping (INEL ; INEL-95/00197; CONF-950740-102; DE96002047)
Paper図書
Ware, A.G.EG and G Idaho, Inc.1995.11.
Other Libraries in Japan

Comparison of ASME Code NB-3200 and NB-3600 results for fatigue analysis of B31.1 branch nozzles (INEL ; INEL-96/00044; CONF-960706-11; TI96009015)

Comparison of ASME Code NB-3200 and NB-3600 results for fatigue analysis of B31.1 branch nozzles (INEL ; INEL-96/00044; CONF-960706-11; TI96009015)
Paper図書
Nitzel, M.E., Ware, A.G., Morton, D.K.Lockheed Idaho Technologies Co.1996.6.
Other Libraries in Japan

Application of environmentally-corrected fatigue curves to nuclear power plant components (INEL ; INEL-96/00105; CONF-960706-10; DE96009012)

Application of environmentally-corrected fatigue curves to nuclear power plant components (INEL ; INEL-96/00105; CONF-960706-10; DE96009012)
Paper図書
Ware, A.G., Morton, D.K., Nitzel, M.E.Lockheed Idaho Technologies Co.1996.
Other Libraries in Japan

Man Ray : 1890 - 1976

Man Ray : 1890 - 1976
Paper図書
essays by Emmanuelle de l'Ecotais and Katherine Ware ; a personal portrait by André Breton ; edited by Manfred HeitingTaschen2004
Other Libraries in Japan

PRELIMINARY EVALUATION OF SNUBBER SINGLE FAILURES. (NUREG ; NUREG/CR-6027)

PRELIMINARY EVALUATION OF SNUBBER SINGLE FAILURES. (NUREG ; NUREG/CR-6027)
Paper図書
WARE, A.G.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1993.
Other Libraries in Japan

NONLINEAR ION-MIXING-MODE PARTICLE TRANSPORT IN THE DISSIPATIVE TRAPPED ELECTRON REGIME. (UW ; UW-CPTC-93-5)

NONLINEAR ION-MIXING-MODE PARTICLE TRANSPORT IN THE DISSIPATIVE TRAPPED ELECTRON REGIME. (UW ; UW-CPTC-93-5)
Paper図書
WARE, A.S.(et al.)1993.
Other Libraries in Japan

PROBABILISTIC BASED DESIGN RULES FOR INTERSYSTEM LOCAS IN ABWR PIPING. (EGG ; EGG-M-92638)

PROBABILISTIC BASED DESIGN RULES FOR INTERSYSTEM LOCAS IN ABWR PIPING. (EGG ; EGG-M-92638)
Paper図書
WARE, A.G.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1993.
Other Libraries in Japan

COMPONENT EVALUATION FOR INTERSYSTEM LOSS-OF-COOLANT ACCIDENTS IN ADVANCED LIGHT WATER REACTORS. (NUREG ; NUREG/CR-6121)

COMPONENT EVALUATION FOR INTERSYSTEM LOSS-OF-COOLANT ACCIDENTS IN ADVANCED LIGHT WATER REACTORS. (NUREG ; NUREG/CR-6121)
Paper図書
WARE, A.G.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1994.
Other Libraries in Japan
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