Heat pipe measurement systems and methods
AssigneeWestinghouse Electric Corp.
InventorsGregory Edward Joseph Kinzler, Jeffrey L. Arndt
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Abstract
Systems and methods for related to heat pipe flow measurement are disclosed. In some embodiments, a heat pipe flow measurement may be used in a method for controlling a nuclear reactor. The method may include measuring a first operating parameter associated with a flow of a working fluid within a heat pipe of the nuclear reactor and determining, based on the first operating parameter, a second operating parameter associated with an amount of thermal energy transferred by the heat pipe.
Claims20
A method for operating a nuclear reactor, comprising:
- measuring a first operating parameter associated with a flow of a working fluid within a heat pipe of the nuclear reactor;
- and
- determining, based on the first operating parameter, a second operating parameter associated with an amount of thermal energy transferred by the heat pipe.
A method for transferring heat with a heat pipe system, comprising:
- determining a rate of thermal energy transfer within a heat pipe based on a measured parameter indicative of fluid flow within a portion of the heat pipe;
- exchanging a portion of the thermal energy as heat between a transfer section of the heat pipe and an environment surrounding the transfer section;
- and
- determining the exchanged portion of the thermal energy based on the rate of thermal energy transfer.
A measurement system, comprising:
- an eddy current sensor configured to be positioned around a portion of a heat pipe;
- and
- a control circuit configured to energize the eddy current sensor at a measurement frequency to determine a flow rate of a working fluid within the portion the heat pipe.
Dependencies are inferred from the claim text.