Status of Alloy 800H in Considerations for the Gen IV Nuclear Energy Systems

被引：28
作者：
Ren, Weiju [1 ]
Swindeman, Robert [2 ]
机构：
[1] Oak Ridge Natl Lab, Mat Sci & Technol Div, Oak Ridge, TN 37831 USA
[2] Cromtech, Oak Ridge, TN 37831 USA
来源：
JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME | 2014年 / 136卷 / 05期
关键词：
HIGH-TEMPERATURE ALLOYS; CREEP; BEHAVIOR; RUPTURE; EMBRITTLEMENT; COMPONENTS; HELIUM; STEELS;
D O I：
10.1115/1.4025093
中图分类号：
TH [机械、仪表工业];
学科分类号：
0802 ;
摘要：
Alloy 800H is currently under consideration for applications in the next generation nuclear plant (NGNP) at operational temperatures above 750 degrees C. This paper first describes service requirements of the nuclear system for structural materials; and then an extensive review of Alloy 800H 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.
引用
收藏
页数：12
相关论文
共 75 条
[1]  
ABB/Combustion Engineering Inc. Bechtel National Inc. Gas-Cooled Reactor Associates General Atomics Massachusetts Institute of Technology Oak Ridge National Laboratory Stone & Webster Engineering Corp., 1994, DOEGTMHR100002 ABB C
[2]  
[Anonymous], 1974, ORNL5014
[3]  
[Anonymous], 1975, COMMUNICATION
[4]  
[Anonymous], 1993, METALLISCHE HTR KOMP
[5]  
Aplin P. F, 1985, 850127 ERA
[6]  
AREVA NP Inc, 2008, 129097380001 AREVA N
[7]  
ASME Boiler and Pressure Vessel Committee, 2011, ASME BIOL PRESS VESS
[8]  
Baldwin D. H., 1986, DESIGN DATA REFERENC
[9]   PRODUCTION AND WELDING TECHNOLOGY OF SOME HIGH-TEMPERATURE NICKEL-ALLOYS IN RELATION TO THEIR PROPERTIES [J].
BASSFORD, TH ;
HOSIER, JC .
NUCLEAR TECHNOLOGY, 1984, 66 (01) :35-43
[10]  
Bloom E.E., 1976, RAD DAMAGE METALS, P295
12345678