Author:
Gonzalez H.C.,Fortis A.M.,Blewitt T.H.
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference19 articles.
1. Irradiation growth in annealed zircaloy-2
2. Properties of Reactor Materials and the Effects of Irradiation Damage;Buckley,1961
3. Physical Metallurgy of Reactor Fuel Elements;Kelly,1973
4. Dimensional changes of unstressed Zircaloy-2 and Zr-2.5 wt % Nb specimens in a fast neutron flux
Cited by
5 articles.
订阅此论文施引文献
订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. High-dose irradiation growth kinetics at 448 K in a zirconium alloy;Journal of Nuclear Materials;2000-06
2. Irradiation growth kinetics in 235U-doped zirconium;Journal of Nuclear Materials;1996-04
3. Recovery of irradiation growth in annealed Zr-1.5 at% al;Journal of Nuclear Materials;1988-08
4. Irradiation Growth of Metals and Alloys;Modern Problems in Condensed Matter Sciences;1986
5. A neutron irradiation growth device and high temperature loop in the reactor RAI;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;1985-09