IC 7981 Development Of A Simulated High-Temperature Nuclear Loop ? Summary

The National Institute for Occupational Safety and Health (NIOSH)
J. P. McGee
Organization:
The National Institute for Occupational Safety and Health (NIOSH)
Pages:
21
File Size:
7387 KB
Publication Date:
Jan 1, 1960

Abstract

As part of a joint U.S. Atomic Energy Commission-Federal Bureau of Mines program for using nuclear energy to supply process heat, a simulated nuclear loop has been constructed to test components. This loop has been operated for more than 1,800 hours at 100 p.s.i.g. Of this period, 23 hours were at 2,500° F. and higher; 540 at 2,000° to 2,500° F.; 840 at 1,500° to 2,000° F.; 200 at 1,000° to 1,500° F.; and 260 below 1,000° F. Leakage at flanges and welds was not a serious problem. A helium-recycle system with gas temperatures of 2,300° to 2,500° F. and a static pressure of 250 p.s.i.g. appears feasible. Difficulties were encountered with the recycle compressor due to thermal distortion of the impeller and shaft. The use of sealed bearings limits compressor operation to the life of the bearings.
Citation

APA: J. P. McGee  (1960)  IC 7981 Development Of A Simulated High-Temperature Nuclear Loop ? Summary

MLA: J. P. McGee IC 7981 Development Of A Simulated High-Temperature Nuclear Loop ? Summary. The National Institute for Occupational Safety and Health (NIOSH), 1960.

Export
Purchase this Article for $25.00

Create a Guest account to purchase this file
- or -
Log in to your existing Guest account