Heavy-Section Steel Technology Program: Semiannual progress report for April--September 1994. Volume 11, Number 2
- Oak Ridge National Lab., TN (United States)
The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission (NRC) by Oak Ridge National Laboratory (ORNL). The program focus is on the development and validation of technology for the assessment of fracture-prevention margins in commercial nuclear reactor pressure vessels. The HSST Program is organized in seven tasks: (1) program management, (2) constraint effects analytical development and validation, (3) evaluation of cladding effects, (4) ductile-to-cleavage fracture-mode conversion, (5) fracture analysis methods development and applications, (6) material property data and test methods, and (7) integration of results. The program tasks have been structured to place emphasis on the resolution fracture issues with near-term licensing significance. Resources to execute the research tasks are drawn from ORNL with subcontract support from universities and other research laboratories. Close contact is maintained with the sister Heavy-Section Steel Irradiation (HSSI) Program at ORNL and with related research programs both in the US and abroad. This report provides an overview of principal developments in each of the seven program tasks from April 1994 to September 1994.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering Technology; Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 226072
- Report Number(s):
- NUREG/CR-4219-Vol.11-No.2; ORNL/TM-9593/V11&N2; ON: TI96010062; TRN: AHC29610%%114
- Resource Relation:
- Other Information: PBD: Apr 1996
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
STEELS
FRACTURE PROPERTIES
WATER COOLED REACTORS
PRESSURE VESSELS
PROGRESS REPORT
REACTOR MATERIALS
FRACTURE MECHANICS
MATERIALS TESTING
RESEARCH PROGRAMS
PHYSICAL RADIATION EFFECTS
MATHEMATICAL MODELS
STRESS INTENSITY FACTORS
CRACK PROPAGATION
RELIABILITY
MITIGATION