Japanese Activities Concerning Nuclear Codes and Standards—Part IISource: Journal of Pressure Vessel Technology:;2006:;volume( 128 ):;issue: 001::page 64Author:Yasuhide Asada
DOI: 10.1115/1.2138063Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This series of papers has been issued to give general views on recent Japanese activities related to nuclear codes and standards. Part II of the series describes component aging aspects and future trends. The component aging aspects include evaluation methods for vessels based on elastic-plastic fracture mechanics, environmental fatigue evaluation guidelines and inspection and evaluation guidelines for reactor internals. With respect to future trends, the development of the International Thermonuclear Experimental Reactor code and the System-Based Code are introduced.
keyword(s): Fatigue , Inspection , Safety , Engineering standards , Evaluation methods , Vessels , Japan Society of Mechanical Engineers , Nuclear power stations , Design , Industrial plants AND Fracture mechanics ,
|
Collections
Show full item record
| contributor author | Yasuhide Asada | |
| date accessioned | 2017-05-09T00:21:27Z | |
| date available | 2017-05-09T00:21:27Z | |
| date copyright | February, 2006 | |
| date issued | 2006 | |
| identifier issn | 0094-9930 | |
| identifier other | JPVTAS-28463#64_1.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/134555 | |
| description abstract | This series of papers has been issued to give general views on recent Japanese activities related to nuclear codes and standards. Part II of the series describes component aging aspects and future trends. The component aging aspects include evaluation methods for vessels based on elastic-plastic fracture mechanics, environmental fatigue evaluation guidelines and inspection and evaluation guidelines for reactor internals. With respect to future trends, the development of the International Thermonuclear Experimental Reactor code and the System-Based Code are introduced. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Japanese Activities Concerning Nuclear Codes and Standards—Part II | |
| type | Journal Paper | |
| journal volume | 128 | |
| journal issue | 1 | |
| journal title | Journal of Pressure Vessel Technology | |
| identifier doi | 10.1115/1.2138063 | |
| journal fristpage | 64 | |
| journal lastpage | 70 | |
| identifier eissn | 1528-8978 | |
| keywords | Fatigue | |
| keywords | Inspection | |
| keywords | Safety | |
| keywords | Engineering standards | |
| keywords | Evaluation methods | |
| keywords | Vessels | |
| keywords | Japan Society of Mechanical Engineers | |
| keywords | Nuclear power stations | |
| keywords | Design | |
| keywords | Industrial plants AND Fracture mechanics | |
| tree | Journal of Pressure Vessel Technology:;2006:;volume( 128 ):;issue: 001 | |
| contenttype | Fulltext |