Cladding separate effects study [electronic resource] : HSST seventh irradiation series
- Published:
- Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1986.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description:
- Pages: 47 : digital, PDF file
- Additional Creators:
- Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- The existence of a layer of tough weld overlay cladding on the interior of a light-water reactor pressure vessel could mitigate the damage caused during certain overcooling transients. This would occur if the cladding can keep a short surface flaw, which would otherwise become long, from growing either by impeding crack initiation or by arresting a running crack. Two aspects of cladding behavior critical to assessing its potential benefit are being examined within the HSST Program: irradiation effects on cladding toughness and the response of mechanically loaded, flawed structures in the presence of a cladding. A two-phase irradiation experiment is being conducted. In the first phase, Charpy impact and tensile specimens from a single-wire, submerged-arc stainless steel weld overlay were irradiated to 2 /times/ 10/sup 23/ neutrons/m/sup 2/ (>1 MeV) at 288/degree/C. Typical, good quality pressure vessel cladding exhibited very little irradiation-induced degradation. In the second phase of irradiations, now in progress, a commercially produced three-wire series-arc weldment is being evaluated under identical irradiation and testing conditions as the first series. In addition, 0.5T compact specimens of both weldments and higher fluences are being examined. The specimens for Phase 2 have been successfully irradiated and all testing should be completed by the end of FY 1987.
- Report Numbers:
- E 1.99:conf-8612174-4
conf-8612174-4 - Subject(s):
- Other Subject(s):
- Reactor Vessels
- Crack Propagation
- Stainless Steel-308
- Fracture Mechanics
- Stainless Steel-309
- Charpy Test
- Ductility
- Irradiation
- Microstructure
- Plates
- Radiation Effects
- Temperature Effects
- Water Cooled Reactors
- Alloys
- Chromium Alloys
- Chromium-Nickel Steels
- Containers
- Crystal Structure
- Destructive Testing
- Heat Resistant Materials
- Heat Resisting Alloys
- High Alloy Steels
- Impact Tests
- Iron Alloys
- Iron Base Alloys
- Materials
- Materials Testing
- Mechanical Properties
- Mechanical Tests
- Mechanics
- Nickel Alloys
- Reactors
- Stainless Steels
- Steel-Cr20ni11
- Steels
- Tensile Properties
- Testing
- Note:
- Published through SciTech Connect.
01/01/1986.
"conf-8612174-4"
"DE89010264"
Vessel integrity review group meeting, Oak Ridge, TN, USA, 2 Dec 1986.
Corwin, W.R. - Funding Information:
- AC05-84OR21400
View MARC record | catkey: 14462719