Published January 1986
| Version v1
Report
Restricted
Heavy-Section Steel Technology Program. Semiannual progress report, April-September 1985. Volume 2
Description
The studies relate to all areas of the technology of materials fabricated into thick-section primary-coolant containment systems of light-water-cooled nuclear power reactors. The focus is on the behavior and structural integrity of steel pressure vessels containing cracklike flaws. The program is organized into ten tasks: (1) program management, (2) fracture methodology and analysis, (3) material characterization and properties, (4) environmentally assisted crack-growth studies, (5) crack-arrest technology, (6) irradiation effects studies, (7) cladding evaluations, (8) intermediate vessel tests and analysis, (9) thermal-shock technology, and (10) pressurized-thermal-shock technology. 111 refs., 125 figs., 38 tabs
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A11/MF A01 - GPO as TI86005187.
Files
Additional details
Publishing Information
- Imprint Pagination
- 227 p.
- Report number
- NUREG/CR--4219-Vol.2
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17061756
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- BWR TYPE REACTORS; CLADDING; CRACK PROPAGATION; FRACTURE MECHANICS; FRACTURE PROPERTIES; IRRADIATION; MANAGEMENT; MATHEMATICAL MODELS; MECHANICAL PROPERTIES; PHYSICAL PROPERTIES; PHYSICAL RADIATION EFFECTS; PWR TYPE REACTORS; REACTOR MATERIALS; RESEARCH PROGRAMS; STEELS; THERMAL SHOCK
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; DEPOSITION; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICS; POWER REACTORS; RADIATION EFFECTS; REACTORS; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- ORNL/TM--9593/V2.