| contributor author | Ren, Weiju | |
| contributor author | Swindeman, Robert | |
| date accessioned | 2017-05-09T01:12:08Z | |
| date available | 2017-05-09T01:12:08Z | |
| date issued | 2014 | |
| identifier issn | 0094-9930 | |
| identifier other | pvt_136_05_054001.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/156195 | |
| description abstract | Alloy 800 H is currently under consideration for applications in the next generation nuclear plant (NGNP) at operational temperatures above 750 آ°C. This paper first describes service requirements of the nuclear system for structural materials; and then an extensive review of Alloy 800 H is given on its codification with respect to development and research history, mechanical behavior and design allowables, metallurgical aging resistance, environmental effect considerations, data requirements and availability, weldments, as well as many other aspects relevant to the intended nuclear application. Finally, further research and development activities to support the materials qualification are suggested. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Status of Alloy 800 H in Considerations for the Gen IV Nuclear Energy Systems | |
| type | Journal Paper | |
| journal volume | 136 | |
| journal issue | 5 | |
| journal title | Journal of Pressure Vessel Technology | |
| identifier doi | 10.1115/1.4025093 | |
| journal fristpage | 54001 | |
| journal lastpage | 54001 | |
| identifier eissn | 1528-8978 | |
| tree | Journal of Pressure Vessel Technology:;2014:;volume( 136 ):;issue: 005 | |
| contenttype | Fulltext | |