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REVIEW OF PROPOSED METHODOLOGY FOR A RISK-INFORMED RELAXATION TO ASME SECTION XI-APPENDIX G. (S&T Issue 2013-25)(CD-ROM) (DE20131038486 ; DE20131038486; PVP2010-25010)

REVIEW OF PROPOSED METHODOLOGY FOR A RISK-INFORMED RELAXATION TO ASME SECTION XI-APPENDIX G. (S&T Issue 2013-25)(CD-ROM) (DE20131038486 ; DE20131038486; PVP2010-25010)
紙図書
DICKSON, T.(et al.)2010.
全国の図書館
  • 著者標目DICKSON, T.

Impact of the heat transfer coefficient on pressurized thermal shock [microform] / prepared by C.F. Boyd, T. Dickson

Impact of the heat transfer coefficient on pressurized thermal shock [microform] / prepared by C.F. Boyd, T. Dickson
マイクロ図書
1999<YCA-Y 3.N 88:10/1667>
国立国会図書館

HFIR vessel probabilistic fracture mechanics analysis ORNLTM13303 DE98 054251

HFIR vessel probabilistic fracture mechanics analysis ORNLTM13303 DE98 054251
マイクロ規格・テクニカルリポート類
Cheverton, R. D, Dickson, T. L1997<LS-DE98/054251>
国立国会図書館

Validation of favor code linear elastic fracture solutions for finite-length flaw geometries CONF-950740-16 DE95 009034

Validation of favor code linear elastic fracture solutions for finite-length flaw geometries CONF-950740-16 DE95 009034
紙マイクロ規格・テクニカルリポート類
Dickson, T. L, Keeney, J. A, Bryson, J. W1995<LS-DE95/009034>
国立国会図書館全国の図書館

Development of a shallow-flaw fracture assessment methodology for nuclear reactor pressure vessels CONF-9609114-1 DE96 008663

Development of a shallow-flaw fracture assessment methodology for nuclear reactor pressure vessels CONF-9609114-1 DE96 008663
紙マイクロ規格・テクニカルリポート類
Bass, B. R, Bryson, J. W, Dickson, T. L, McAfee, W. J, Pennell, W. E1996<LS-DE96/008663>
国立国会図書館全国の図書館

EVALUATION OF MARGINS IN THE ASME RULES FOR DEFINING THE P-T CURVE FOR A RPV. (ORNL ; ORNL/CP-100102; DE00001747)

EVALUATION OF MARGINS IN THE ASME RULES FOR DEFINING THE P-T CURVE FOR A RPV. (ORNL ; ORNL/CP-100102; DE00001747)
紙図書
DICKSON, T.L.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1998.
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  • 著者標目DICKSON, T.L.

HFIR VESSEL LIFE EXTENSION WITH ENLARGED HB-2 AND HB-4 BEAM TUBES. (ORNL ; ORNL/TM-13698; DE00003297)

HFIR VESSEL LIFE EXTENSION WITH ENLARGED HB-2 AND HB-4 BEAM TUBES. (ORNL ; ORNL/TM-13698; DE00003297)
紙図書
DICKSON, T.L.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1998.
全国の図書館
  • 著者標目DICKSON, T.L.

Introduction to chemistry 8th ed

Introduction to chemistry 8th ed
紙図書
T.R. DicksonJ. Wiley1999
全国の図書館
  • 著者標目Dickson, T. R. (Thomas R.)

Inclusion of unstable ductile tearing and extrapolated crack-arrest toughness data in PWR vessel integrity assessment / prepared by T.L. Dickson, R.D. Cheverton, and D.K. Shum

Inclusion of unstable ductile tearing and extrapolated crack-arrest toughness data in PWR vessel integrity assessment / prepared by T.L. Dickson, R.D. Cheverton, and D.K. Shum
マイクロ図書
1990<YCA-Y 3.N 88:25/5473>
国立国会図書館
  • 著者標目Dickson, T. L Cheverton, R. D Shum, D. K ...

PRESSURIZED THERMAL SHOCK PROBABILISTIC FRACTURE MECHANICS SENSITIVITY ANALYSIS FOR YANKEE ROWE REACTOR PRESSURE VESSEL. (NUREG ; NUREG/CR-5782)

PRESSURIZED THERMAL SHOCK PROBABILISTIC FRACTURE MECHANICS SENSITIVITY ANALYSIS FOR YANKEE ROWE REACTOR PRESSURE VESSEL. (NUREG ; NUREG/CR-5782)
紙図書
DICKSON, T.L.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1993.
全国の図書館
  • 著者標目DICKSON, T.L.

Ｉｎｔｒｏｄｕｃｔｉｏｎ　ｔｏ　ｃｈｅｍｉｓｔｒｙ：６ｔｈ　ｅｄ．

Ｉｎｔｒｏｄｕｃｔｉｏｎ　ｔｏ　ｃｈｅｍｉｓｔｒｙ：６ｔｈ　ｅｄ．
紙図書
Ｄｉｃｋｓｏｎ，Ｔ・Ｒ／著John Wiley & Sons１９９１．７
全国の図書館

FAVOR: A NEW FRACTURE MECHANICS CODE FOR REACTOR PRESSURE VESSELS SUBJECTED TO PRESSURIZED THERMAL SHOCK (CONF ; CONF-930702-10)

FAVOR: A NEW FRACTURE MECHANICS CODE FOR REACTOR PRESSURE VESSELS SUBJECTED TO PRESSURIZED THERMAL SHOCK (CONF ; CONF-930702-10)
紙図書
DICKSON, T.L. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1993.
全国の図書館
  • 著者標目DICKSON, T.L.

GENERIC ANALYSES FOR EVALUATION OF LOW CHARPY UPPER-SHELF ENERGY EFFECTS ON SAFETY MARGINS AGAINST FRACTURE OF REACTOR PRESSURE VESSEL MATERIALS. (NUREG ; NUREG/CR-6023)

GENERIC ANALYSES FOR EVALUATION OF LOW CHARPY UPPER-SHELF ENERGY EFFECTS ON SAFETY MARGINS AGAINST FRACTURE OF REACTOR PRESSURE VESSEL MATERIALS. (NUREG ; NUREG/CR-6023)
紙図書
DICKSON, T.L.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1993.
全国の図書館
  • 著者標目DICKSON, T.L.

Introduction to chemistry pbk. 7th ed

Introduction to chemistry pbk. 7th ed
紙図書
T.R. DicksonWileyc1995
全国の図書館
  • 著者標目Dickson, T. R. (Thomas R.)

"Stress-Intensity-Factor Influence Coefficients for Axially Oriented Semielliptical Inner-Surface Flaws in Clad Pressure Vessels (Rj/t=10)."

"Stress-Intensity-Factor Influence Coefficients for Axially Oriented Semielliptical Inner-Surface Flaws in Clad Pressure Vessels (Rj/t=10)."
紙図書
DICKSON, T. L.//KEENEY, J. A.OAK RIDGE NATIONAL LABORATORY1993/12/23.
全国の図書館
  • 著者標目DICKSON, T. L.//KEENEY, J. A.

INCLUSION OF UNSTABLE DUCTILE TEARING AND EXTRAPOLATED CRACK-ARREST TOUGHNESS DATA IN PWR VESSEL INTEGRITY ASSESSMENT. (NUREG ; NUREG/CR-5473)

INCLUSION OF UNSTABLE DUCTILE TEARING AND EXTRAPOLATED CRACK-ARREST TOUGHNESS DATA IN PWR VESSEL INTEGRITY ASSESSMENT. (NUREG ; NUREG/CR-5473)
紙図書
DICKSON, T.L.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1990.
全国の図書館
  • 著者標目DICKSON, T.L.

EFFECTS OF CLADDING ON PROPAGATION OF FINITE-LENGTH FLAWS IN PTS ANALYSIS (CONF ; CONF-930803-12)

EFFECTS OF CLADDING ON PROPAGATION OF FINITE-LENGTH FLAWS IN PTS ANALYSIS (CONF ; CONF-930803-12)
紙図書
KEENEY, J.A.// DICKSON, T.L. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1993.
全国の図書館
  • 著者標目KEENEY, J.A. DICKSON, T.L.

STRESS-INTENSITY-FACTOR INFLUENCE COEFFICIENTS FOR AXIAL AND CIRCUMFERENTIAL FLAWS IN REACTOR PRESSURE VESSELS (CONF ; CONF-930702-4)

STRESS-INTENSITY-FACTOR INFLUENCE COEFFICIENTS FOR AXIAL AND CIRCUMFERENTIAL FLAWS IN REACTOR PRESSURE VESSELS (CONF ; CONF-930702-4)
紙図書
BRYSON, J.W.// DICKSON, T.L. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1993.
全国の図書館
  • 著者標目BRYSON, J.W. DICKSON, T.L.

APPLICATION OF PROBABILISTIC FRACTURE ANALYSIS TO RESIDUAL LIFE EVALUATION OF EMBRITTLED REACTOR VESSELS (CONF ; CONF-920375-14)

APPLICATION OF PROBABILISTIC FRACTURE ANALYSIS TO RESIDUAL LIFE EVALUATION OF EMBRITTLED REACTOR VESSELS (CONF ; CONF-920375-14)
紙図書
DICKSON, T.L.// SIMONEN, F.A. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1992.
全国の図書館
  • 著者標目DICKSON, T.L. SIMONEN, F.A.

POTENTIAL EFFECT OF FRACTURE TECHNOLOGY IPTS(INTEGRATED PRESSURIZED THERMAL SHOCK) ANALYSIS (FRACTURE TOUGHNESS: KLA AND KLC AND WARM PRESTRESSING) (CONF ; CONF-9010196-2-VUGRAPHS)

POTENTIAL EFFECT OF FRACTURE TECHNOLOGY IPTS(INTEGRATED PRESSURIZED THERMAL SHOCK) ANALYSIS (FRACTURE TOUGHNESS: KLA AND KLC AND WARM PRESTRESSING) (CONF ; CONF-9010196-2-VUGRAPHS)
紙図書
DICKSON, T.L. (OAK RIDGE NATIONAL LAB., TN (USA))1990.
全国の図書館
  • 著者標目DICKSON, T.L.