Published September 1967 | Version v1
Book

Irradiation Behaviour of Experimental Fuel Assemblies of UO2 -PuO2 and ThO2-PuO2

Creators

  • 1. Atomic Energy of Canada, Ltd,, Chalk River, ON (Canada)

Description

The results are described of detailed examination of eleven Zircaloy-2 clad oxide fuel elements after irradiation in NRX. Six elements were of UO2 -PuO2 (up to 1.39 wt. % PuO2 and these are compared with two enriched UO2 elements after operation at heat ratings (∫T0T8λ(θ)dθ) up to 63 W cm-1 to an average burn-up of 1550 MWd/Te oxide. The other three elements were ThO2 -PuO2 containing up to 1.93 wt.% PuO2 and operating at ratings up to 77 W cm-1 (∫T0TSλ(θ)dθ) to a maximum burn-up of 1260 MWd/Te oxide. The results reported comprise profilometer data, fission gas release, metallographic examination and autoradiography (both beta-gamma and alpha). (author)

Part of:
Plutonium as a Reactor Fuel. Proceedings of a Symposium on the Use of Plutonium as a Reactor Fuel

Additional details

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (International Atomic Energy Agency (IAEA))
Imprint Title
Plutonium as a Reactor Fuel. Proceedings of a Symposium on the Use of Plutonium as a Reactor Fuel
Imprint Pagination
876 p.
Series
Proceedings Series
Journal Page Range
p. 421-438
ISSN
0074-1884

Conference

Title
Symposium on the Use of Plutonium as a Reactor Fuel
Dates
13-17 Mar 1967
Place
Brussels (Belgium)

Optional Information

Notes
12 refs., 10 figs., 6 tabs.
Secondary number(s)
IAEA-SM--88/29