Cladding and duct materials for advanced nuclear recycle reactors

被引：0
作者：
T. R. Allen
J. T. Busby
R. L. Klueh
S. A. Maloy
M. B. Toloczko
机构：
[1] University of Wisconsin-Madison,Engineering Physics Department
[2] Oak Ridge National Laboratory,undefined
[3] Los Alamos National Laboratory,undefined
[4] Pacific Northwest National Laboratory,undefined
来源：
JOM | 2008年 / 60卷
关键词：
Fast Reactor; Oxide Dispersion Strengthened; DBTT; Irradiation Creep; Oxide Dispersion Strengthened Steel;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
The expanded use of nuclear energy without risk of nuclear weapons proliferation and with safe nuclear waste disposal is a primary goal of the Global Nuclear Energy Partnership (GNEP). To achieve that goal the GNEP is exploring advanced technologies for recycling spent nuclear fuel that do not separate pure plutonium, and advanced reactors that consume transuranic elements from recycled spent fuel. The GNEP’s objectives will place high demands on reactor clad and structural materials. This article discusses the materials requirements of the GNEP’s advanced nuclear recycle reactors program.
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页码：15 / 23
页数：8
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