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The effects of composition and heat treatment on hardening and embrittlement of reactor pressure vessel steels [microform] / prepared by G.R. Odette ... [et al.] NUREG/CR-6778

The effects of composition and heat treatment on hardening and embrittlement of reactor pressure vessel steels [microform] / prepared by G.R. Odette ... [et al.] NUREG/CR-6778
マイクロ図書
2003<YCA-Y 3.N 88:25/6778>
国立国会図書館

Damage analysis and fundamental studies for fusion reactor materials development for the period March 1, 1991--February 28, 1994. Final report. PROGRESS REPT DOE/ER/52143-T3 DE95 008728

Damage analysis and fundamental studies for fusion reactor materials development for the period March 1, 1991--February 28, 1994. Final report. PROGRESS REPT DOE/ER/52143-T3 DE95 008728
マイクロ規格・テクニカルリポート類
Odette, G. R, Lucas, G. E1995<LS-DE95/008728>
国立国会図書館

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

Electron irradiation-induced mechanical property changes in reactor pressure vessel alloys ANL/MSD/CP-86950 DE96 006741 CONF-95115575

Electron irradiation-induced mechanical property changes in reactor pressure vessel alloys ANL/MSD/CP-86950 DE96 006741 CONF-95115575
マイクロ規格・テクニカルリポート類
Alexander, D. E, Rehn, L. E, Odette, G. R, Lucas, G. E1995<LS-DE96/006741>
国立国会図書館

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

Effects of helium pre-implantation on the microstructure and mechanical properties of irradiated 316 stainless steel PNL-SA-25670 DE95 007162 CONF-94114460

Effects of helium pre-implantation on the microstructure and mechanical properties of irradiated 316 stainless steel PNL-SA-25670 DE95 007162 CONF-94114460
紙マイクロ規格・テクニカルリポート類
Toloczko, M. B, Tedeski, G. R, Lucas, G. E, Odette, G. R, Stoller, R. E1994<LS-DE95/007162>
国立国会図書館全国の図書館

ELECTRON IRRADIATION-INDUCED MECHANICAL PROPERTY CHANGES IN REACTOR PRESSURE VESSEL ALLOYS (ANL ; ANL/MSD/CP-86950)

ELECTRON IRRADIATION-INDUCED MECHANICAL PROPERTY CHANGES IN REACTOR PRESSURE VESSEL ALLOYS (ANL ; ANL/MSD/CP-86950)
紙図書
ALEXANDER, D.E.// REHN, L.E.// ODETTE, G.R.// LUCAS, G.E. (ARGONNE NATIONAL LAB., IL (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1995.
全国の図書館
  • 著者標目ALEXANDER, D.E. REHN, L.E. ODETTE, G.R. LUCAS, G.E.

DAMAGE ANALYSIS AND FUNDAMENTAL STUDIES FOR FUSION REACTOR MATERIALS DEVELOPMENT FOR THE PERIOD MARCH 1, 1991-FEBRUARY 28, 1994. FINAL REPORT (DOE ; DOE/ER/52143-T3)

DAMAGE ANALYSIS AND FUNDAMENTAL STUDIES FOR FUSION REACTOR MATERIALS DEVELOPMENT FOR THE PERIOD MARCH 1, 1991-FEBRUARY 28, 1994. FINAL REPORT (DOE ; DOE/ER/52143-T3)
紙図書
ODETTE, G.R.// LUCAS, G.E. (CALIFORNIA UNIV., SANTA BARBARA, CA (UNITED STATES). DEPT. OF CHEMICAL AND NUCLEAR ENGINEERING)United States. Dept. of Energy(United States. Dept. of Energy)1995.
全国の図書館
  • 著者標目ODETTE, G.R. LUCAS, G.E.

STUDIES OF LOW TEMPERATURE, LOW FLUX RADIATION EMBRITTLEMENT OF NUCLEAR REACTOR STRUCTURAL MATERIALS (DOE ; DOE/ER/12895-T1)

STUDIES OF LOW TEMPERATURE, LOW FLUX RADIATION EMBRITTLEMENT OF NUCLEAR REACTOR STRUCTURAL MATERIALS (DOE ; DOE/ER/12895-T1)
紙図書
ODETTE, G.R.// LUCAS, G.E. (CALIFORNIA UNIV., SANTA BARBARA, CA (UNITED STATES). DEPT. OF CHEMICAL AND NUCLEAR ENGINEERING)United States. Dept. of Energy(United States. Dept. of Energy)1993.
全国の図書館
  • 著者標目ODETTE, G.R. LUCAS, G.E.

DAMAGE ANALYSIS AND FUNDAMENTAL STUDIES FOR FUSION REACTOR MATERIALS DEVELOPMENT (DOE ; DOE/ER/52143-T2)

DAMAGE ANALYSIS AND FUNDAMENTAL STUDIES FOR FUSION REACTOR MATERIALS DEVELOPMENT (DOE ; DOE/ER/52143-T2)
紙図書
ODETTE, G.R.// LUCAS, G.E. (CALIFORNIA UNIV., SANTA BARBARA, CA (UNITED STATES). DEPT. OF CHEMICAL AND NUCLEAR ENGINEERING)United States. Dept. of Energy(United States. Dept. of Energy)1993.
全国の図書館
  • 著者標目ODETTE, G.R. LUCAS, G.E.

MATERIALS IRRADIATION SUBPANEL REPORT TO BESAC NEUTRON SOURCES AND RESEARCH PANEL (BNL ; BNL-48820)

MATERIALS IRRADIATION SUBPANEL REPORT TO BESAC NEUTRON SOURCES AND RESEARCH PANEL (BNL ; BNL-48820)
紙図書
BIRTCHER, R.C.// GOLAND, A.N.// LOTT, R.// ODETTE, G.R. (BROOKHAVEN NATIONAL LAB., UPTON, NY (UNITED STATES))Brookhaven National Laboratory(Brookhaven National Laboratory)1992.
全国の図書館
  • 著者標目BIRTCHER, R.C. GOLAND, A.N. LOTT, R. ODETTE, G.R.

DAMAGE ANALYSIS AND FUNDAMENTAL STUDIES FOR FUSION REACTOR MATERIALS DEVELOPMENT (DOE ; DOE/ER/52143-T1)

DAMAGE ANALYSIS AND FUNDAMENTAL STUDIES FOR FUSION REACTOR MATERIALS DEVELOPMENT (DOE ; DOE/ER/52143-T1)
紙図書
ODETTE, G.R.// LUCAS, G.E. (CALIFORNIA UNIV., SANTA BARBARA, CA (UNITED STATES). DEPT. OF CHEMICAL AND NUCLEAR ENGINEERING)United States. Dept. of Energy(United States. Dept. of Energy)1991.
全国の図書館
  • 著者標目ODETTE, G.R. LUCAS, G.E.

ANALYSIS OF HYDROGEN ATTACK ON PRESSURE-VESSEL STEELS. FINAL REPORT. (DOE ; DOE-ET-10747-T1)

ANALYSIS OF HYDROGEN ATTACK ON PRESSURE-VESSEL STEELS. FINAL REPORT. (DOE ; DOE-ET-10747-T1)
紙図書
ODETTE, G.R.United States. Dept. of Energy(United States. Dept. of Energy)1982.
全国の図書館
  • 著者標目ODETTE, G.R.

DAFS CONTRIBUTION QUARTERLY SPECIMEN MATRIX IN THE AD-2 IRRADIATION EXPERIMENT. (HEDL ; HEDL-6817)

DAFS CONTRIBUTION QUARTERLY SPECIMEN MATRIX IN THE AD-2 IRRADIATION EXPERIMENT. (HEDL ; HEDL-6817)
紙図書
ODETTE, G.R.Hanford Engineering Development Laboratory(Hanford Engineering Development Laboratory)1980.
全国の図書館
  • 著者標目ODETTE, G.R.

REACTOR MATERIALS PERFORMANCE PREDICTIONS USING DAMAGE FUNCTIONS: ANALYSIS OF FLUENCE LIMIT UNCETRAINTIES. (HEDL ; HEDL-TME-75-43)

REACTOR MATERIALS PERFORMANCE PREDICTIONS USING DAMAGE FUNCTIONS: ANALYSIS OF FLUENCE LIMIT UNCETRAINTIES. (HEDL ; HEDL-TME-75-43)
紙図書
ODETTE, G.R.(et al.)Hanford Engineering Development Laboratory(Hanford Engineering Development Laboratory)1976.
全国の図書館
  • 著者標目ODETTE, G.R.

REACTOR MATERIALS PERFORMANCE PREDICTIONS: A CRITIQUE OF DAMAGE FUNCTIONS ANALYSIS. (HEDL ; HEDL-SA-657)

REACTOR MATERIALS PERFORMANCE PREDICTIONS: A CRITIQUE OF DAMAGE FUNCTIONS ANALYSIS. (HEDL ; HEDL-SA-657)
紙図書
ODETTE, G.R.(et al.)Hanford Engineering Development Laboratory(Hanford Engineering Development Laboratory)1974.
全国の図書館
  • 著者標目ODETTE, G.R.

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

PARTICLE RANGE AND ENERGY DEPOSITION IN MATERIALS CONTAINING VOIDS. (UCLA ; UCLA-34-P-172-10)

PARTICLE RANGE AND ENERGY DEPOSITION IN MATERIALS CONTAINING VOIDS. (UCLA ; UCLA-34-P-172-10)
紙図書
ODETTE, G.R.
全国の図書館
  • 著者標目ODETTE, G.R.

ENERGY DEPENDENT NEUTRON SPUTTERING AND SURFACE DAMAGE CROSS SECTIONS. (CONF ; CONF-760209-18)

ENERGY DEPENDENT NEUTRON SPUTTERING AND SURFACE DAMAGE CROSS SECTIONS. (CONF ; CONF-760209-18)
紙図書
ODETTE, G.R.
全国の図書館
  • 著者標目ODETTE, G.R.

FISSION-FUSION CORRELATIONS FOR SWELLING AND MICROSTRUCTURE IN STAINLESS STEELS... (CONF ; CONF-810831-98-DRAFT)

FISSION-FUSION CORRELATIONS FOR SWELLING AND MICROSTRUCTURE IN STAINLESS STEELS... (CONF ; CONF-810831-98-DRAFT)
紙図書
ODETTE, G.R.
全国の図書館
  • 著者標目ODETTE, G.R.