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
Files
36043296.pdf
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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)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36043296
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; BLISTERS; BURNUP; CLADDING; COEXTRUSION; COMPACTING; FUEL CHANNELS; FUEL ELEMENTS; PERFORMANCE TESTING; POWDER METALLURGY; SNR REACTOR; SWELLING; URANIUM OXIDES U3O8
- Descriptors DEC
- ACTINIDE COMPOUNDS; BREEDER REACTORS; CHALCOGENIDES; DEFORMATION; DEPOSITION; ELEMENTS; EPITHERMAL REACTORS; EXTRUSION; FABRICATION; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS WORKING; METALLURGY; METALS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS; SURFACE COATING; TESTING; URANIUM COMPOUNDS; URANIUM OXIDES
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