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Scandpower, Inc. Patents
Assignee:
Scandpower, Inc.
Address:
Rockville, MD
No. of patents:
16
Patents:












Patent Number Title Of Patent Date Issued
4652420 Hydrogen measuring device March 24, 1987
The aim of the invention is to measure the partial pressure of very small amounts of free hydrogen gas at various sites in the core of a nuclear reactor. A further aim is to construct such a device to be so rugged as to survive in the reactor environment. Another aim is to construct such
4637913 Device for measuring the power in a nuclear reactor January 20, 1987
The device comprises, in addition to a gamma thermometer with two junctions and insulated output conductive wires placed in a traversing sheath, an instrument placed outside the reactor for measuring the total current circulating between at least one of the conductive wires and the sheat
4634570 Process and device for measuring the local thermal power in a nuclear reactor January 6, 1987
This device is intended to measure the thermal power released locally in an area of the core of a nuclear reactor and comprises a conduit in the core of the reactor from the outside which contains a body which absorbs gamma radiations located at the measuring area and associated with a m
4603580 Unicable liquid level sensing system August 5, 1986
Double-junction thermocouple sensors located at axially spaced measurement zones within an elongated probe are interconnected in series to produce a combined output from differential signals generated by the sensors in response to unequal heating of the junctions. Axial heat flow between
4592230 Apparatus for and method of determining the liquid coolant level in a nuclear reactor June 3, 1986
A liquid coolant measuring instrument for a nuclear reactor vessel measures the liquid coolant level by utilizing the thermal characteristics of the medium surrounding the instrument. The instrument has an elongated cylindrical body having a number of difference thermocouples disposed
4567013 Hydrogen measuring device January 28, 1986
A hydrogen measuring apparatus comprising two gamma thermometers. Both gamma thermometers are mounted adjacent and parallel to each other. Each is provided with a plurality of annular enclosed spaces formed in an elongated rod. Each annular space is provided with a hot junction of a
4512949 Power performance monitoring system for nuclear reactor fuel core April 23, 1985
Direct power shape monitoring in parallel with precision power monitoring is effected by use of gamma sensors in the fuel core and signal processing that includes compensation for slow signal response and takes advantage of a substantially direct relationship of sensor signal to linear p
4459045 Gamma thermometer with zircaloy barrier July 10, 1984
Zircaloy metal is utilized to form the heat generating core and internal lining of a high strength pressure barrier for a gamma thermometer. The internal lining which is cross-sectionally smaller than the core, forms a hydrogen gas barrier to prevent deterioration of the low thermal
4440716 In-situ calibration of local power measuring devices for nuclear reactors April 3, 1984
An electrical heater cable is positioned within an assembly of multiple junction thermocouple cables associated with the elongated gamma heated body of a local power measuring unit to electrically heat the body from an external source during a calibration period. The signal outputs of th
4439396 Multijunction difference thermocouples for gamma sensors March 27, 1984
Thermocouple junctions located in the hot and cold regions of an elongated heat conductive body extending through a measurement zone of a power monitoring device, are interconnected in series to provide a differential temperature signal of increased signal strength and fast signal respon
4425297 Gamma ray thermometer for boiling water reactor January 10, 1984
The elongated monolithic radiation absorbing body of a gamma ray sensor has its entire external surface exposed to coolant for establishing a uniform heat sink temperature throughout. Cold junction regions are formed in portions of the elongated body of reduced cross-sectional area suffi
4418035 Coolant condition monitor for nuclear power reactor November 29, 1983
The faster acting junction of a difference junction thermocouple associated with a gamma sensor is located vertically above the other junction to ordinarily monitor local power generation in the fuel core of a nuclear reactor and in response to a reversal in the signal voltage polarity
4411859 Gamma sensor having combined thermal bridge and centering means October 25, 1983
A gamma sensor is supported coaxially in a bore, extending through the core of a nuclear reactor, by centering means which span the annular space between the gamma sensor and the bore. Said centering means also acts as a thermal bridge so that the portion of the gamma sensor contacted by
4411858 Power performance monitoring system for nuclear reactor fuel core October 25, 1983
Direct power shape monitoring in parallel with precision power monitoring is effected by use of gamma sensors in the fuel core and signal processing that includes compensation for slow signal response and takes advantage of a substantially direct relationship of sensor signal to linear p
4356061 Gamma thermometer having combined thermal bridge and centering means October 26, 1982
A gamma thermometer is supported coaxially in a bore, extending through the core of a nuclear reactor, by spring means which span the annular space between the gamma thermometer and the bore. Said spring means acts, in addition, as a thermal bridge, so that the portion of the gamma t
4313792 Miniature gamma thermometer slideable through bore for measuring linear heat generation rate February 2, 1982
A gamma thermometer for use with a nuclear reactor is provided with two thermocouple junctions which are connected so as to output the difference voltage. The two thermocouple junctions are spaced closely enough so that, considering the scale of the nuclear reactor, they experience the s

 
 
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