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ORNL-4191 - the Molten Salt Energy Technologies Web Site

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183<br />

Fig. 15.4. Inner Surface and Crock in Core Outlet Pipe of In-Pile Loop 2. Top side, near core. 250~.<br />

caused by stresses resulting from differential<br />

<strong>the</strong>rmal expansion of <strong>the</strong> loop components.<br />

Calculation of <strong>the</strong> piping stresses in <strong>the</strong> loop<br />

has been made for two conditions' (1) for <strong>the</strong><br />

temperature profile around <strong>the</strong> loop at normal,<br />

full-power in-pile operation, and (2) for <strong>the</strong> temperature<br />

profile observed during a reactor setback<br />

(change from full power to zero in - 1'/* min).<br />

For both conditions (1) and (2) <strong>the</strong> piping stress<br />

analysis indicates that <strong>the</strong> maximum stress from<br />

<strong>the</strong>rmal expansion occurs in <strong>the</strong> core outlet pipe<br />

where <strong>the</strong> failure occurred. For <strong>the</strong> normal operating<br />

condition <strong>the</strong> bending movement produces a<br />

stress of cv 10,000 psi in <strong>the</strong> pipe wall (tension on<br />

<strong>the</strong> top and compression on <strong>the</strong> bottom). For <strong>the</strong><br />

temperature distribution encountered during a<br />

reactor setback, <strong>the</strong> direction of <strong>the</strong> bending movement<br />

is reversed, causing a stress of - 17,000 psi<br />

in <strong>the</strong> pipe wall (compression on top and tension<br />

on <strong>the</strong> bottom).<br />

It appears that two factors could have caused<br />

<strong>the</strong> failure in <strong>the</strong> core outlet pipe. First, <strong>the</strong><br />

section of pipe where failure occurred was at a<br />

temperature of 'v 1350OF. Stress-rupture properties<br />

of Hastelloy N at 13s0°P; (732OC) are below those<br />

at 1200'F (65OOC) used for design purposes, and<br />

<strong>the</strong>se properties are fur<strong>the</strong>r reduced394 by <strong>the</strong><br />

accumulated irradiation dose of -'5 x 10l9 nvt.<br />

Under <strong>the</strong>se conditions (1350'F and 5 x lQ19<br />

nvt), it is estimated that stresses of about 10,000<br />

psi could produce rupture wjthin moderatc times,<br />

possibly of <strong>the</strong> order of days. Fur<strong>the</strong>r, <strong>the</strong> duc-<br />

tility of IIastelloy N is reduced such that strains<br />

of 1 to 3% can result in fracture. Thus <strong>the</strong> <strong>the</strong>rmal<br />

stress of -10,000 psi calculated to exist in <strong>the</strong><br />

outlet pipe at full power nppration may have been<br />

sufficient to cause failure. A second and more<br />

3H. E. McCoy, Jr., and J. R. Weir, Jr., Materznfs de<br />

velopnient for <strong>Molten</strong>-<strong>Salt</strong> Breeder Reactors, OHNL--<br />

TM-1854 (.June 16, 1967).<br />

'H. E. McCoy, Jr., and J. K. Weir, Jr., In- nndEx-<br />

Reactor Stress-ltupture Properties of Hastelloy N<br />

Tubing, <strong>ORNL</strong>-TM-1906 (September 1967).

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