Heavy-Section Steel Technology Program. Quarterly progress report, April-June 1982. [PWR; BWR]
Technical Report
·
OSTI ID:6587572
The three-dimensional finite-element program for elastic-plastic fracture analysis was adapted to the analysis of stainless-steel-clad structures under combined pressure and thermal-shock loads. Subcontractors continued their support of thermal-shock experiments and investigation of fracture mode transitions and crack-arrest testing. Statistical analyses of irradiated Charpy impact specimens were completed, and plans wer made for two new irradiation studies, high-copper welds and stainless steel cladding. Further overcooling accident analyses were made, and preliminary studies of the next thermal-shock experiments were conducted. Preparations for the test of intermediate vessel V-8A continued, objectives were established for three pressurized-thermal-shock (PTS) tests, and procurement activities for the PTS test facility were initiated. Five flawed plates were tested in the stainless steel cladding investigations.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6587572
- Report Number(s):
- NUREG/CR-2751-Vol.2; ORNL/TM-8369-Vol.1; ON: DE83002146
- Country of Publication:
- United States
- Language:
- English
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210100* -- Power Reactors
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Light-Water Moderated
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
BWR TYPE REACTORS
CONTAINERS
CRYSTAL STRUCTURE
FRACTURE PROPERTIES
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IRON BASE ALLOYS
MECHANICAL PROPERTIES
MICROSTRUCTURE
PHYSICAL RADIATION EFFECTS
PRESSURE GRADIENTS
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTORS
RESEARCH PROGRAMS
STEELS
STRESS ANALYSIS
STRESSES
TEST FACILITIES
THERMAL SHOCK
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS