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Effect of cyclic and dynamic loads on carbon steel pipe NUREG/CR-6438 TI96 007099 BMI-2188

Effect of cyclic and dynamic loads on carbon steel pipe NUREG/CR-6438 TI96 007099 BMI-2188
マイクロ規格・テクニカルリポート類
Rudland, D. L, Scott, P. M, Wilkowski, G. M1996<LS-TI96/007099>
国立国会図書館

Evaluation and refinement of leak-rate estimation models NUREG/CR-5128-Rev.1 TI94 015006

Evaluation and refinement of leak-rate estimation models NUREG/CR-5128-Rev.1 TI94 015006
マイクロ規格・テクニカルリポート類
Paul, D. D, Ahmad, J, Scott, P. M, Flanigan, L. F, Wilkowski, G. M1994<LS-TI94/015006>
国立国会図書館

EXPERIMENTAL AND ANALYTICAL ASSESSMENT OF CIRCUMFERENTIALLY SURFACE-CRACKED PIPES UNDER BENDING (NUREG ; NUREG/CR-4872; BMI-2149)

EXPERIMENTAL AND ANALYTICAL ASSESSMENT OF CIRCUMFERENTIALLY SURFACE-CRACKED PIPES UNDER BENDING (NUREG ; NUREG/CR-4872; BMI-2149)
紙図書
SCOTT, P.M./AHMAD, J.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
全国の図書館
  • 著者標目SCOTT, P.M. AHMAD, J.

IRRADIATION ASSISTED STRESS CORROSION OF FUEL ELEMENT COMPONENTS OF A STEAM GENERATING HEAVY WATER REACTOR. (AERE ; AERE-R-12852)

IRRADIATION ASSISTED STRESS CORROSION OF FUEL ELEMENT COMPONENTS OF A STEAM GENERATING HEAVY WATER REACTOR. (AERE ; AERE-R-12852)
紙図書
SCOTT, P.M.(et al.)Atomic Energy Research Establishment(Atomic Energy Research Establishment)1987.
全国の図書館
  • 著者標目SCOTT, P.M.

ASSESSMENT OF DESIGN BASIS FOR LOAD-CARRYING CAPACITY OF WELD-OVERLAY REPAIRS (NUREG ; NUREG/CR-4877; BMI-2150)

ASSESSMENT OF DESIGN BASIS FOR LOAD-CARRYING CAPACITY OF WELD-OVERLAY REPAIRS (NUREG ; NUREG/CR-4877; BMI-2150)
紙図書
SCOTT, P.M.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1987.
全国の図書館
  • 著者標目SCOTT, P.M.

REVIEW OF ENVIRONMENTAL EFFECTS ON PRESSURE VESSEL INTEGRITY. (AERE ; AERE-R-12780)

REVIEW OF ENVIRONMENTAL EFFECTS ON PRESSURE VESSEL INTEGRITY. (AERE ; AERE-R-12780)
紙図書
SCOTT, P.M.Atomic Energy Research Establishment(Atomic Energy Research Establishment)1987.
全国の図書館
  • 著者標目SCOTT, P.M.

CORROSION FATIGUE CHAPTER 8.6 OF THE NEW EDITION OF CORROSION-EDS SHREIR JARMAN AND BERNSTEIN. (AERE ; AERE-R-12284)

CORROSION FATIGUE CHAPTER 8.6 OF THE NEW EDITION OF CORROSION-EDS SHREIR JARMAN AND BERNSTEIN. (AERE ; AERE-R-12284)
紙図書
SCOTT, P.M.Atomic Energy Research Establishment(Atomic Energy Research Establishment)1986.
全国の図書館
  • 著者標目SCOTT, P.M.

DEVELOPMENT OF ENGINEERING CODES OF PRACTICE FOR CORROSION FATIGUE. (AERE ; AERE-R-10480)

DEVELOPMENT OF ENGINEERING CODES OF PRACTICE FOR CORROSION FATIGUE. (AERE ; AERE-R-10480)
紙図書
SCOTT, P.M.(et al.)Atomic Energy Research Establishment(Atomic Energy Research Establishment)1985.
全国の図書館
  • 著者標目SCOTT, P.M.

DEV AND USE OF ELECTROCHEMICAL POTENTIAL MONITORING IN ENVIRONMENT ASSISTED CRACKING TESTS ETC. (AERE ; AERE-R-11741)

DEV AND USE OF ELECTROCHEMICAL POTENTIAL MONITORING IN ENVIRONMENT ASSISTED CRACKING TESTS ETC. (AERE ; AERE-R-11741)
紙図書
SCOTT, P.M.(et al.)Atomic Energy Research Establishment(Atomic Energy Research Establishment)1985.
全国の図書館
  • 著者標目SCOTT, P.M.

OVERVIEW OF DATA REDUCTION AND APPLICATION MODELS FOR CORROSION FATIGUE DATA FOR PRESSURE VESSEL STEELS IN L W R ENVIRONMENTS. (AERE ; AERE-R-11699)

OVERVIEW OF DATA REDUCTION AND APPLICATION MODELS FOR CORROSION FATIGUE DATA FOR PRESSURE VESSEL STEELS IN L W R ENVIRONMENTS. (AERE ; AERE-R-11699)
紙図書
SCOTT, P.M.Atomic Energy Research Establishment(Atomic Energy Research Establishment)1985.
全国の図書館
  • 著者標目SCOTT, P.M.

STRESS CORROSION AND CORROSION FATIGUE IN WATER REACTOR ENVIRONMENTS. (AERE ; AERE-R-11867)

STRESS CORROSION AND CORROSION FATIGUE IN WATER REACTOR ENVIRONMENTS. (AERE ; AERE-R-11867)
紙図書
SCOTT, P.M.Atomic Energy Research Establishment(Atomic Energy Research Establishment)1985.
全国の図書館
  • 著者標目SCOTT, P.M.

REVIEW OF ENVIRONMENT SENSITIVE FRACTURE IN WATER REACTOR MATERIALS. (AERE ; AERE-R-11385)

REVIEW OF ENVIRONMENT SENSITIVE FRACTURE IN WATER REACTOR MATERIALS. (AERE ; AERE-R-11385)
紙図書
SCOTT, P.M.Atomic Energy Research Establishment(Atomic Energy Research Establishment)1984.
全国の図書館
  • 著者標目SCOTT, P.M.

CORROSION FATIGUE OF PRESSURE VESSEL STEELS IN LWR ENVIRONMENTS - INFLUENCE OF STEEL SULPHUR CONTENT. (AERE ; AERE-R-10964)

CORROSION FATIGUE OF PRESSURE VESSEL STEELS IN LWR ENVIRONMENTS - INFLUENCE OF STEEL SULPHUR CONTENT. (AERE ; AERE-R-10964)
紙図書
SCOTT, P.M.(et al.)Atomic Energy Research Establishment(Atomic Energy Research Establishment)1983.
全国の図書館
  • 著者標目SCOTT, P.M.

INTERIM REPORT ON THE INFLUENCE OF MATERIAL VARIABLES ON CORROSION FATIGUE CRACK GROWTH IN REACTOR PRESSURE VESSEL STEELS IN PWR PRIMARY WATER. (AERE ; AERE-R-10421)

INTERIM REPORT ON THE INFLUENCE OF MATERIAL VARIABLES ON CORROSION FATIGUE CRACK GROWTH IN REACTOR PRESSURE VESSEL STEELS IN PWR PRIMARY WATER. (AERE ; AERE-R-10421)
紙図書
SCOTT, P.M.(et al.)Atomic Energy Research Establishment(Atomic Energy Research Establishment)1982.
全国の図書館
  • 著者標目SCOTT, P.M.

CHEMISTRY EFFECTS IN CORROSION FATIGUE. (AERE ; AERE-R-10481)

CHEMISTRY EFFECTS IN CORROSION FATIGUE. (AERE ; AERE-R-10481)
紙図書
SCOTT, P.M.(et al.)Atomic Energy Research Establishment(Atomic Energy Research Establishment)1982.
全国の図書館
  • 著者標目SCOTT, P.M.

Fatigue crack growth in austenitic stainless steel (ND-R ; ND-R-802(S))

Fatigue crack growth in austenitic stainless steel (ND-R ; ND-R-802(S))
紙図書
McMinn, A., Scott, P.M.UKAEA Nuclear Power Development Establishment1982.6.
全国の図書館
  • 著者標目McMinn, A. Scott, P.M.

INFLUENCE OF WATER CHEMISTRY ON FATIGUE CRACK PROPAGATION. (AD ; AD-A106-116)

INFLUENCE OF WATER CHEMISTRY ON FATIGUE CRACK PROPAGATION. (AD ; AD-A106-116)
紙図書
SCOTT,P.M.(et al.)1981.
全国の図書館

Influence of Water Chemistry on Fatigue Crack Propagation in LWR Pressure Vessel Steels (AERE ; AERE-R-10201)

Influence of Water Chemistry on Fatigue Crack Propagation in LWR Pressure Vessel Steels (AERE ; AERE-R-10201)
紙図書
Scott, P.M./Truswell, A.E.Atomic Energy Research Establishment(Atomic Energy Research Establishment)1981.
全国の図書館
  • 著者標目Scott, P.M. Truswell, A.E.

Prediction of Semi-elliptic Crack Shape Development during Fatigue Crack Growth (AERE ; AERE-R-10104)

Prediction of Semi-elliptic Crack Shape Development during Fatigue Crack Growth (AERE ; AERE-R-10104)
紙図書
Scott, P.M./Thorpe, T.W.Atomic Energy Research Establishment(Atomic Energy Research Establishment)1981.
全国の図書館
  • 著者標目Scott, P.M. Thorpe, T.W.

Use of corrosion fatigue data in the assessment of crack growth in large nuclear pressure vessels (AERE ; AERE-R-8642)

Use of corrosion fatigue data in the assessment of crack growth in large nuclear pressure vessels (AERE ; AERE-R-8642)
紙図書
Scott, P.M.Atomic Energy Research Establishment(Atomic Energy Research Establishment)1977.
全国の図書館
  • 著者標目Scott, P.M.
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