Results of [U.sub.0.55][Pu.sub.0.45]N and [U.sub.0.4][Pu.sub.0.6]N mixed mononitride fuel tests in a BOR-60 reactor to burnup 12% h.a

The results of post-reactor studies of [U.sub.0.55][Pu.sub.0.45]N and [U.sub.0.4][Pu.sub.0.6]N mixed mononitride fuel elements (density 85% of the theoretical value) and a helium sublayer are presented. The fuel elements are irradiated in a BOR-60 reactor to burnup 9.4 and 12.1% h.a., respectively,...

Full description

Saved in:
Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2011-10, Vol.110 (6), p.412
Main Authors: Rogozkin, B.D, Stepennova, N.M, Fedorov, Yu. E, Shishkov, M.G, Kryukov, F.N, Kuzmin, S.V, Nikitin, O.N, Belyaeva, A.V, Zabudko, L.M
Format: Article
Language:English
Subjects:
Building materials
Online Access:Get full text
Tags: Add Tag
No Tags, Be the first to tag this record!
Description
Summary:The results of post-reactor studies of [U.sub.0.55][Pu.sub.0.45]N and [U.sub.0.4][Pu.sub.0.6]N mixed mononitride fuel elements (density 85% of the theoretical value) and a helium sublayer are presented. The fuel elements are irradiated in a BOR-60 reactor to burnup 9.4 and 12.1% h.a., respectively, with power density 430 and 540 W/cm. All fuel elements remained hermetic; the ChS-68 steel cladding (20% cold deformation) retained excess plasticity. The maximum zone of interaction between the cladding and the fuel and fission products did not exceed 15 ism. The swelling rate of [U.sub.0.4][Pu.sub.0.6]N and [U.sub.0.55][Pu.sub.0.45]N fuel was 1.1 and 0.68%/% burnup, respectively. The gas release did not exceed 19.3 and 19%. The steel damage dose was 43 dpa. The character of the porosity distribution in the fuel affects the swelling and gas release.
ISSN:1063-4258
1573-8205