Japanese activities concerning nuclear codes and standards - Part II

被引：17

作者：

Asada, Y ^{[1
]}

机构：

[1] Univ Tokyo, Thermal & Nucl Power Engn Soc, Tokyo 1050001, Japan

来源：

JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME | 2006年 / 128卷 / 01期

关键词：

D O I：

10.1115/1.2138063

中图分类号：

TH [机械、仪表工业];

学科分类号：

0802 ;

摘要：

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.

引用

页码：64 / 70

页数：7