Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964 Page: 44
xvi, 166 p. : ill. ; 28 cm.View a full description of this report.
Extracted Text
The following text was automatically extracted from the image on this page using optical character recognition software:
44
gas was sampled and analyzed. Although there is slight indication of
radioactivity in the gas, it is believed at this time that the outgassing
can be tolerated. This test is continuing.
Thermocouple Test Assembly for Temperature Safety Channel
A device has been developed which permits the insertion of a test
signal into the input of the reactor temperature safety instrument channels
without disconnecting any wires and which is compatible with the require-
ments for physical isolation of redundant safety channels. The device con-
sists of a vacuum thermocouple assembly of the type frequently used to
measure the rms value of rf currents and an associated transformer and push
button switch. The vacuum thermocouple consists of a fine-wire heater sup-
ported at each end with a fine-wire thermocouple attached to its center by
a ceramic bead. This whole assembly is sealed in an evacuated glass bulb.
By passing a current through the heater, an electromotive force (emf) is
generated by the thermocouple. The emf generated is approximately 0.07
my/ma, with the maximum permissible current being 200 ma. Thus the full-
range output is approximately 14 my, which is equivalent to 560F on the
Chromel-Alumel thermocouple scale. Leads of the device may be connected
to simulate either a temperature increase or decrease, depending on
the polarity of the voltage output. A schematic diagram of the device
is shown in Fig. 2.11.
UNCLASSIFIED
ORNL-DWG 64-3999
NORMALLY OPEN
DOUBLE BREAK VACUUM
PUSH BUTTON THERMOCOUPLE
, o
420v AC OO9
6.3 v AC
SEC.
12 v A C3oI
308 L- - - - - -
S THERMOCOUPLE
CONNECTIONTEST
JACKFig. 2.11.
Channel.Thermocouple Test Assembly for Temperature Safety
Upcoming Pages
Here’s what’s next.
Search Inside
This report can be searched. Note: Results may vary based on the legibility of text within the document.
Tools / Downloads
Get a copy of this page or view the extracted text.
Citing and Sharing
Basic information for referencing this web page. We also provide extended guidance on usage rights, references, copying or embedding.
Reference the current page of this Report.
Oak Ridge National Laboratory. Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964, report, July 1964; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc100344/m1/62/: accessed April 23, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.