| contributor author | T. R. Mager | |
| contributor author | D. M. Moon | |
| contributor author | J. D. Landes | |
| date accessioned | 2017-05-08T23:03:39Z | |
| date available | 2017-05-08T23:03:39Z | |
| date copyright | May, 1977 | |
| date issued | 1977 | |
| identifier issn | 0094-9930 | |
| identifier other | JPVTAS-28148#238_1.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/90363 | |
| description abstract | Fatigue crack growth rate tests conducted in primary grade reactor coolant at 550°F (288°C) on A533 Grade B Class 1 steel (HSST Plate 02) showed an increase in growth rates at a frequency of 1 cpm over previous results obtained at frequencies of 60 cpm and higher. This increase, the general character of the crack growth rate versus the ΔK curve, and the results from fractographic studies, all indicated that stress corrosion cracking might have occurred for this material and environment. However, a specimen loaded statically in a PWR environment showed no static load crack growth. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Fatigue Crack Growth Characteristics of A533 Grade B Class I Plate in an Environment of High-Temperature Primary Grade Nuclear Reactor Water | |
| type | Journal Paper | |
| journal volume | 99 | |
| journal issue | 2 | |
| journal title | Journal of Pressure Vessel Technology | |
| identifier doi | 10.1115/1.3454526 | |
| journal fristpage | 238 | |
| journal lastpage | 247 | |
| identifier eissn | 1528-8978 | |
| keywords | Fatigue cracks | |
| keywords | Nuclear reactors | |
| keywords | Water | |
| keywords | High temperature | |
| keywords | Fracture (Materials) | |
| keywords | Pressurized water reactors | |
| keywords | Frequency | |
| keywords | Nuclear reactor coolants | |
| keywords | Steel | |
| keywords | Stress corrosion cracking AND Stress | |
| tree | Journal of Pressure Vessel Technology:;1977:;volume( 099 ):;issue: 002 | |
| contenttype | Fulltext | |
