Published August 1993 | Version v1
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Powder metallurgy development at SRL

Creators

  • 1. Savannah River Laboratory, E.I. du Pont de Nemours and Co., Aiken, SC (United States)

Description

The Savannah River Laboratory (SRL) is developing a powder metallurgy (P/M) process for manufacturing reactor-grade fuel tubes containing high wt % U3O8-Al cores clad with 8001 aluminum. The P/M cores are made by isostatic compaction. They are assembled in billets, outgassed, and hot-extruded using conventional coextrusion techniques. Cores have been compacted with up to 100% U3O8 and tubes extruded with 80 wt % oxide cores. Irradiation tests have been made using P/M core tubes in the Savannah River reactors. These tubes contained U3O8 concentrations up to 59 wt % and no significant swelling or blistering occurred. The tubes were irradiated to ∼ 40% burnup or 1.6x1021 fissions/cc of core. This report discusses both small-scale and production tests for high-density P/M fuel development. The purpose of the P/M development program at SRL is to: determine the maximum U3O8 content that can be fabricated into thin wall tubes, irradiate high-density tubes to high burnup and assess irradiation and dimensional stability, continue metal forming studies for extrusion and drawing, and evaluate hydrostatic extrusion and hydrostatically assisted drawing of P/M core tubes. Experimental results of testing the fuel assemblies performance so far indicate that: cores containing fine (-325 mesh) U3O8 and aluminum powders can be made practically free of high-density areas using the outlined P/M pre blending and sieving techniques. U3O8-Al cores can be isostatically compacted with up to 100 wt U3O8 and tubes successfully extruded with up to 80 wt oxide; fission gas blistering of U3O8-Al P/M tubes as indicated by the blister tests is a function of fissions/cc of U3O8 in the core; Decreasing the fission density of oxide increases the threshold temperature for blister formation; U3O8-Al P/M fuel tubes with up to 59 wt U3O8 have been successfully irradiated in SRP reactor to 1.6 x 1021 fissions/cc of core or 7 x 1020 fissions/cc of U3O8 small-scale metal forming tests sufficiently mock up production operations so that variables can be initially tested in the laboratory; parametric metal forming studies show a relationship between measurable variables of tooling temperature, half die angle and core composition. Lower temperatures and larger die angles 50-60 deg C favor extrusion of high density fuel tubes

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Part of:
Proceedings of the 1978 international meeting on reduced enrichment for research and test reactors

Additional details

Publishing Information

Imprint Title
Proceedings of the 1978 international meeting on reduced enrichment for research and test reactors
Imprint Pagination
238 p.
Journal Page Range
p. 112-132
Report number
ANL/RERTR/TM--1

Conference

Title
1978 international meeting on reduced enrichment for research and test reactors
Dates
9-10 Nov 1978
Place
Argonne, IL (United States)

Optional Information

Contract/Grant/Project number
Contract W-31-109-Eng-38
Notes
9 figs, 1 tab
Secondary number(s)
CONF--781151; INIS-XA-C--022