ORNL-1771 - Oak Ridge National Laboratory

ORNL-1771 - Oak Ridge National Laboratory ORNL-1771 - Oak Ridge National Laboratory

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I ORNL-LR-DWG 3092 CALCULATIONS EXTRAPOLATION ~ 0. 02 04 06 OB 10 12 14 16 18 20 Ar (cml Fig. 2.2. Effect of Space Interval Size on Com- puted Critical Mass. Fig, 2.3. Beryllium Test Block. effects of severe thermal stresses in beryllium at temperatures between 1000 and 1300"F.9~ lo There has been serious concern as to whether cracking or distortion in the beryllium would prove to be a major problem. Therefore a test on the beryllium block shown in Fig. 2.3 was devised to investigate the effects of power (and hence thermal) cycling. The test loop used is shown in Fig. 2.4. Heat was generated in the beryllium block by simple electrical-resi stance heating with a current of about 15,000 amp through the beryllium block. Sodium flowed from an electromagnetic pump to the block inlet header, upward through the lower 9R. W. Bussard et al., The Moderator Cooling System lor the Reflector-Moderated Reactor, ORNL-1517 (Jan. 22, 1954). 'OF. A. Field, Temperature Gradient und Thermal Stresses in Heat Generating Bodies, ORNL CF-54-5-196 (May 21, 1954). 27

ANP QUARTERLY PROGRESS REPORT SURGE TANK- tube bank to the corresponding holes in the be- ryllium block, through the upper tube back into the outlet header, out to the radiator section, and back to the pump. Banks of tubes were used to duct the sodium to and from the block to minimize the flow of electrical current through the sodium inlet and outlet header tanks. A bypass filter arrangement was provided, as well as bypass cooling flow to the sodium-filled lugs connected to the transformer bus bars. The high-power-density volume heat source coupled with transverse sodium flow through the drilled holes gave a high thermal gradient around the holes. During the course of the test the power density was cycled regularly by alternating the 28 ELECl Fig. 2.4. Beryllium Thermal Stress Test Apparatus. UNCLASSIFIED ORNL-LR-DWG 3093 -kvo TRANSFORMER \ 111 ' ~ ~ ~ / ~ A I R - C O OCOPPER L E D BUS BAR operating conditions as shown in Table 2.6, which also compares the operating conditions for the thermal stress test with those for the CFRE. The test included an initial 100-hr period at a constant high power density followed by power cycling at the rate of one cycle per day. The changes from one power level to the other were, in all cases, performed at a fairly uniform rate in a 1-min interval. The test was concluded after 1000 hr of operation, including 36 cycles. The beryllium sample is now being examined by the Metallurgy Division for dimensional stability and evidence of mass transfer, corrosion, or erosion. Visual inspection of the sample after the test indicated that no distortion, cracking, or erosion of the beryllium had taken place.

I<br />

<strong>ORNL</strong>-LR-DWG 3092<br />

CALCULATIONS<br />

EXTRAPOLATION ~<br />

0. 02 04 06 OB 10 12 14 16 18 20<br />

Ar (cml<br />

Fig. 2.2. Effect of Space Interval Size on Com-<br />

puted Critical Mass.<br />

Fig, 2.3. Beryllium Test Block.<br />

effects of severe thermal stresses in beryllium at<br />

temperatures between 1000 and 1300"F.9~ lo There<br />

has been serious concern as to whether cracking<br />

or distortion in the beryllium would prove to be a<br />

major problem. Therefore a test on the beryllium<br />

block shown in Fig. 2.3 was devised to investigate<br />

the effects of power (and hence thermal) cycling.<br />

The test loop used is shown in Fig. 2.4. Heat<br />

was generated in the beryllium block by simple<br />

electrical-resi stance heating with a current of<br />

about 15,000 amp through the beryllium block.<br />

Sodium flowed from an electromagnetic pump to<br />

the block inlet header, upward through the lower<br />

9R. W. Bussard et al., The Moderator Cooling System<br />

lor the Reflector-Moderated Reactor, <strong>ORNL</strong>-1517 (Jan.<br />

22, 1954).<br />

'OF. A. Field, Temperature Gradient und Thermal<br />

Stresses in Heat Generating Bodies, <strong>ORNL</strong> CF-54-5-196<br />

(May 21, 1954).<br />

27

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