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ORNL-4191 - the Molten Salt Energy Technologies Web Site

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221<br />

Fig. 18.3. Hastellay N Containing 14C Annealed 1 hr at 240OOF. Autoradiographs made in situ on lightly etched<br />

surface using Kodak NTE liquid emulsion; 312-hr exposure. Reduced 38%.<br />

The thin film of precipitate in Fig. 18.5a is of N. However, <strong>the</strong> zirconium addition appears to<br />

<strong>the</strong> face-centered cubic type with “Ti 20’’ existing be very desirable from <strong>the</strong> standpoint of improving<br />

as <strong>the</strong> “spines” and polyhedral particles. The <strong>the</strong> resistance of <strong>the</strong> material to embrittlement<br />

threadlike morphology of <strong>the</strong> face-centered cubic by neutron irradiation. For this reason, we are<br />

precipitate is seen in Fig. 18.Sh.<br />

continuing studies to determine how we can im-<br />

The final objectives of this work are to identify prove <strong>the</strong> weldatility of zirconium-bearing alloys.<br />

all precipitates present and to correlate <strong>the</strong>ir for- One tool that we are using in our study is <strong>the</strong><br />

mation with <strong>the</strong> mechanical behavior ot <strong>the</strong> alloy. Gleeble. The Gleeble permits us to assess <strong>the</strong><br />

hot ductility of <strong>the</strong> base material as it is being<br />

18.4. HOT-DUCTILITY STUDIES<br />

OF ZI RCONIUM-BEARING MODlFlED<br />

HASTELLOY N<br />

subjected to a <strong>the</strong>rmal cycle simulating that received<br />

by <strong>the</strong> heat-affected zone (HAZ) of a weldment.<br />

Specimens are fractured, on heating, at increas-<br />

D. A. Canonico<br />

ing temperatures until <strong>the</strong>y no longer exhibit any<br />

~<br />

Our previous work4 has shown that zirconium<br />

4Meta1s and Ceramics Div. Ann. Progr. Rep. J~me 30,<br />

additions cause weld-metal cracking in Hastelloy I 96 7, ORNT .-4 1 70.

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