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Models for embrittlement recovery due to annealing of reactor pressure vessel steels NUREG/CR-6327 TI95 011539 MCS-950302

Models for embrittlement recovery due to annealing of reactor pressure vessel steels NUREG/CR-6327 TI95 011539 MCS-950302
マイクロ規格・テクニカルリポート類
Eason, E. D, Wright, J. E, Nelson, E. E, Odette, G. R, Mader, E. V1995<LS-TI95/011539>
国立国会図書館

Multivariable modeling of pressure vessel and piping J-R data / prepared by E.D. Eason, J.E. Wright, E.E. Nelson

Multivariable modeling of pressure vessel and piping J-R data / prepared by E.D. Eason, J.E. Wright, E.E. Nelson
マイクロ図書
1991<YCA-Y 3.N 88:25/5729>
国立国会図書館

Improved model for predicting J-R curves from Charpy data [microform] : phase I final report / prepared by E.D. Eason, E.E. Nelson

Improved model for predicting J-R curves from Charpy data [microform] : phase I final report / prepared by E.D. Eason, E.E. Nelson
マイクロ図書
1989<YCA-Y 3.N 88:25/5356>
国立国会図書館

MODELS FOR EMBRITTLEMENT RECOVERY DUE TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS. (NUREG ; NUREG/CR-6327)

MODELS FOR EMBRITTLEMENT RECOVERY DUE TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS. (NUREG ; NUREG/CR-6327)
紙図書
EASON, E.D.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1995.
全国の図書館

Forwards rept,NUREG/CR-6327, "Models for Embrittlement Recovery Due to Annealing of Reactor Pressure Vessel Steels."

Forwards rept,NUREG/CR-6327, "Models for Embrittlement Recovery Due to Annealing of Reactor Pressure Vessel Steels."
紙図書
EASON, E. D.MODELING & COMPUTER SERVICES1995/03/22.
全国の図書館
  • 著者標目EASON, E. D.

MULTIVARIABLE MODELING OF PRESSURE VESSEL AND PIPING J-R DATA. (NUREG ; NUREG/CR-5729)

MULTIVARIABLE MODELING OF PRESSURE VESSEL AND PIPING J-R DATA. (NUREG ; NUREG/CR-5729)
紙図書
EASON, E.D.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1991.
全国の図書館

IMPROVED MODEL FOR PREDICTING J-R CURVES FROM CHARPY DATA. PHASE 1. (FINAL REPORT. OCT 88-MAR 89.) (NUREG ; NUREG/CR-5356; MCS-890301)

IMPROVED MODEL FOR PREDICTING J-R CURVES FROM CHARPY DATA. PHASE 1. (FINAL REPORT. OCT 88-MAR 89.) (NUREG ; NUREG/CR-5356; MCS-890301)
紙図書
EASON, E.D.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1989.
全国の図書館

Probability of failure in BWR reactor coolant piping: Probabilistic treatment of stress corrosion cracking in 304 and 316NG BWR piping weldments (UCID ; UCID-20914-VOL.3)

Probability of failure in BWR reactor coolant piping: Probabilistic treatment of stress corrosion cracking in 304 and 316NG BWR piping weldments (UCID ; UCID-20914-VOL.3)
紙図書
Failure Analysis Associates, Palo Alto, CA (USA)(Failure Analysis Associates, Palo Alto, CA (USA))1986.
全国の図書館

Improved embrittlement correlations for reactor pressure vessel steels [microform] / prepared by E.D. Eason, J.E. Wright, G.R. Odette

Improved embrittlement correlations for reactor pressure vessel steels [microform] / prepared by E.D. Eason, J.E. Wright, G.R. Odette
マイクロ図書
1998<YCA-Y 3.N 88:25/6551>
国立国会図書館
  • 著者標目Eason, E. D. (Ernest D.) Wright, J. E. (Jo...

DESIGN, COST, AND PERFORMANCE COMPARISONS OF SEVERAL SOLAR-THERMAL SYSTEMS FOR PROCESS HEAT. VOLUME II. CONCENTRATORS. (SAND ; SAND-79-8280)

DESIGN, COST, AND PERFORMANCE COMPARISONS OF SEVERAL SOLAR-THERMAL SYSTEMS FOR PROCESS HEAT. VOLUME II. CONCENTRATORS. (SAND ; SAND-79-8280)
紙図書
EASON, E.D.Sandia National Laboratories(Sandia National Laboratories)1981.
全国の図書館

Mod 10,increasing contract ceiling,extending period of performance & amending listed sections,to "Improved Irradiation Embrittlement Correlations."

Mod 10,increasing contract ceiling,extending period of performance & amending listed sections,to "Improved Irradiation Embrittlement Correlations."
紙図書
EASON, E. D.//MACE, M. H.MODELING & COMPUTER SERVICES,NRC OFFICE OF ADMINISTRATION (ADM)1995/04/14.
全国の図書館
  • 著者標目EASON, E. D.//MACE, M. H.

"Preliminary Evaluation of Annealing Recovery Data," informal draft rept.

"Preliminary Evaluation of Annealing Recovery Data," informal draft rept.
紙図書
EASON, E. D.//NELSON, E. E.MODELING & COMPUTER SERVICES1992/06/04.
全国の図書館
  • 著者標目EASON, E. D.//NELSON, E. E.

MODELS FOR EMBRITTLEMENT RECOVERY DUE TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS.

MODELS FOR EMBRITTLEMENT RECOVERY DUE TO ANNEALING OF REACTOR PRESSURE VESSEL STEELS.
紙図書
EASON, E. D.//MADER, E. V.//NELSON, E. E.//ODETTE, G. R.//WRIGHT, J. E.CALIFORNIA, UNIV. OF, SANTA BARBARA, CA,MODELING & COMPUTER SERVICES1995/05/31.
全国の図書館
  • 著者標目EASON, E. D.//MADER, E. V.//NELSON, E. E./...

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