𝔖 Bobbio Scriptorium
✦   LIBER   ✦

A polycrystalline modeling of the mechanical behavior of neutron irradiated zirconium alloys

✍ Scribed by Fabien Onimus; Jean-Luc Béchade

Book ID
108186790
Publisher
Elsevier Science
Year
2009
Tongue
English
Weight
600 KB
Volume
384
Category
Article
ISSN
0022-3115

No coin nor oath required. For personal study only.

📜 SIMILAR VOLUMES

A study of the annealing behavior of neu
A study of the annealing behavior of neutron irradiated graphite
✍ T.D. Burchell; P.J. Pappano; J.P. Strizak 📂 Article 📅 2011 🏛 Elsevier Science 🌐 English ⚖ 652 KB

Recycle is being considered as a waste mitigation option for irradiated graphite from gas cooled reactors. Thermal annealing was performed on irradiated graphite samples to establish what fraction of in-crystal (displacement damage) and ex-crystal (pore generation) damage could be recovered. The sam