The fabrication and irradiation of plutonium-containing inert matrix fuels for the ‘Once Though Then Out’ experiment

Seven plutonium containing inert matrix fuel (IMF) capsules were prepared for an irradiation experiment in the high flux reactor. In the irradiation experiment, named once-through-then-out, both spinel-based and zirconia-based targets are irradiated up to a plutonium burnup of about 200 GW d m −3, c...

Full description

Saved in:
Bibliographic Details
Published in:Journal of nuclear materials 2003-06, Vol.319, p.118-125
Main Authors: Schram, R.P.C, van der Laan, R.R, Klaassen, F.C, Bakker, K, Yamashita, T, Ingold, F
Format: Article
Language:English
Subjects:
Applied sciences
Energy
Exact sciences and technology
Fuels
Nuclear fuels
Preparation and processing of nuclear fuels
Citations: Items that this one cites
Items that cite this one
Online Access:Get full text
Tags: Add Tag
No Tags, Be the first to tag this record!
Description
Summary:Seven plutonium containing inert matrix fuel (IMF) capsules were prepared for an irradiation experiment in the high flux reactor. In the irradiation experiment, named once-through-then-out, both spinel-based and zirconia-based targets are irradiated up to a plutonium burnup of about 200 GW d m −3, corresponding to a Pu depletion of 50–60%. Both micro and macrodispersed spinel targets are tested, the zirconia targets are of the homogeneous type. In this paper, the fabrication routes of the IMF pellets for this irradiation are described in detail. The results of the dimensional measurements, density measurements, ceramographies and X-ray images of the samples are given. Some preliminary results of the irradiation are included.
ISSN:0022-3115
1873-4820
DOI:10.1016/S0022-3115(03)00143-0