METALLURGICAL INVESTIGATIONS ON THE CLADDING FAILURE IN JPDR PRESSURE VESSEL. V. THE EFFECT OF FREQUENCY OF LOADING ON THE FATIGUE CRACK PROPAGATION OF A LOW ALLOY STEEL IN HIGH TEMPERATURE, DEIONIZED WATER. (in Japanese)
Technical Report
·
OSTI ID:4664621
- Research Organization:
- Japan Atomic Energy Research Inst., Tokyo
- NSA Number:
- NSA-26-048360
- OSTI ID:
- 4664621
- Report Number(s):
- JAERI-Memo-4022
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-72
- Country of Publication:
- Japan
- Language:
- Japanese
Similar Records
METALLURGICAL INVESTIGATIONS ON THE CLADDING FAILURE IN THE JPDR PRESSURE VESSEL. III. EFFECT OF TEMPERATURE ON THE FATIGUE CRACK PROPAGATION IN A LOW ALLOY STEEL IN DEIONIZED WATER.
METALLURGICAL INVESTIGATIONS ON THE CLADDING FAILURE IN THE JPDR PRESSURE VESSEL. IV. THE EFFECT OF FREQUENCY OF LOADING ON THE FATIGUE OF LOW ALLOY STEEL IN RECIRCULATING DEIONIZED WATER ENVIRONMENT.
METALLURGICAL INVESTIGATIONS ON THE CLADDING FAILURE IN THE JPDR PRESSURE VESSEL. II. A STUDY ON THE PITTING CORROSION IN HIGH TEMPERATURE WATER OF A LOW ALLOY STEEL WITHIN THE SIMULATED CRACKS IN THE PROTECTIVE WELD OVERLAY.
Technical Report
·
Thu Jan 01 00:00:00 EST 1970
·
OSTI ID:4664621
METALLURGICAL INVESTIGATIONS ON THE CLADDING FAILURE IN THE JPDR PRESSURE VESSEL. IV. THE EFFECT OF FREQUENCY OF LOADING ON THE FATIGUE OF LOW ALLOY STEEL IN RECIRCULATING DEIONIZED WATER ENVIRONMENT.
Technical Report
·
Thu Jan 01 00:00:00 EST 1970
·
OSTI ID:4664621
METALLURGICAL INVESTIGATIONS ON THE CLADDING FAILURE IN THE JPDR PRESSURE VESSEL. II. A STUDY ON THE PITTING CORROSION IN HIGH TEMPERATURE WATER OF A LOW ALLOY STEEL WITHIN THE SIMULATED CRACKS IN THE PROTECTIVE WELD OVERLAY.
Technical Report
·
Thu Jan 01 00:00:00 EST 1970
·
OSTI ID:4664621
+1 more
Related Subjects
N50210* -Metals
Ceramics
& Other Materials-Metals & Alloys-Corrosion & Erosion & Surface Phenomena
N78241 -Power Reactor Development-Commercial Power Reactors-Cooling Systems-Non-breeder Boiling Water
COOLANTS
CRACKS
FATIGUE
HIGH TEMPERATURE
JPDR REACTOR
PRESSURE VESSELS
STEEL-ASTM-A302
STRESSES
WATER
WATER COOLED REACTORS
STEEL/fatigue crack propagation in ASTM A302B
in high- temperature deionized water
effects of cyclic loading frequency on
WATER/ effects of high-temperature deionized
on fatigue crack propagation in ASTM A302B steel as function of cyclic loading frequency
JAPANESE POWER DEMONSTRATION REACTOR/pressure vessel cladding failure in
Ceramics
& Other Materials-Metals & Alloys-Corrosion & Erosion & Surface Phenomena
N78241 -Power Reactor Development-Commercial Power Reactors-Cooling Systems-Non-breeder Boiling Water
COOLANTS
CRACKS
FATIGUE
HIGH TEMPERATURE
JPDR REACTOR
PRESSURE VESSELS
STEEL-ASTM-A302
STRESSES
WATER
WATER COOLED REACTORS
STEEL/fatigue crack propagation in ASTM A302B
in high- temperature deionized water
effects of cyclic loading frequency on
WATER/ effects of high-temperature deionized
on fatigue crack propagation in ASTM A302B steel as function of cyclic loading frequency
JAPANESE POWER DEMONSTRATION REACTOR/pressure vessel cladding failure in