Fixed incore wide range neutron sensor

Claim 2

A wide range neutron detector, comprising: (a) a sealed chamber, having two spaced electrodes positioned therein, hermetically sealed with a seal which is disposed within a reactor vessel, adjacent the core of said reactor in an environment having neutron flux which is substantially at least two decades below the neutron flux at the location of the detector; (b) an ionizable gas, disposed within the space between the electrodes, pressurized to a pressure above six atmospheres; and (c) a layer of a mixture of an active material and a breeding material, positioned within the chamber, the active material and breeding material being respectively U-235 and U-234, the layer having a thickness of at least 0.2 milligrams per square centimeter.

Claim 3

The detector of claim 1, wherein the seal is comprised of a ceramic material brazed to a metallic material.

Claim 4

The detector of claim 1, wherein the detector is disposed within a nuclear reactor core having a neutron flux in the range of from 10 3 to 10 14 nv, with the detector so disposed that the seal is external to the reactor core and experiences a neutron flux which is at least two decades below the neutron flux in the reactor core.

Claim 5

The detector of claim 1, wherein the seal is positioned at least 24 inches outside the reactor core, to thereby diminish aging of the seal due to neutron bombardment, so the life of the seal is much greater than the life of the sensor.

Claim 6

the detector of claim 1, wherein the ionizable gas is pressurized to a pressure ranging from 6.0 atmospheres to 20.0 atmospheres.

Claim 7

The detector of claim 1, wherein the ionizable gas is pressurized to a pressure of 14.7 atmospheres.

Claim 8

The detector of claim 1, wherein the layer of the material has a thickness in the range of from 0.20 to 0.80 milligrams per square centimeter.

Claim 9

The detector of claim 1, wherein the layer has a thickness preferably in the range of from 0.40 to 0.80 milligrams per square centimeter.

Claim 10

The detector of claim 1, wherein the mixture of active and breeding material is comprised of a ratio ranging from 70:30 to 90:10 of a mixture of U-234:U-235.

Claim 11

The detector of claim 1, wherein the layer of the mixture of the active and breeding material is comprised of ratio of 21% U-235 to 79% U-234.

Claim 12

The detector of claim 1, wherein the space between the electrodes is in the range of from 0.008 to 0.020 inches.

Claim 13

The detector of claim 1, wherein the space between the electrodes is at least 0.010 inches.

Claim 14

The detector of claim 1, wherein the detector is designed to be sensitive to neutron fluxes in the range from 10 -9 % to 100% of the full power operation of the source providing the neutron flux.

Claim 15

The detector of claim 1, wherein one of the electrodes includes a layer of a mixture of active material and a breeding material.

Claim 16

The detector of claim 1, wherein each of the electrodes includes a layer of the mixture of an active material and a breeding material.

Claim 19

The detector of claim 1, wherein the space is provided with a well controlled ionizable gas, selected to have a pressure high enough to provide, in conjunction with the selected layer of uranium coating, adequate sensitivity for the counting range.

Claim 20

The method of claim 16, wherein said pressurizing step includes pressurizing with a well controlled ionizable gas selected from the group of gases including argon and helium.

Claim 21

The method of claim 16, wherein said pressurizing step includes pressurizing a well controlled ionizable gas to a pressure of 14.7 atmospheres.

Claim 22

The detector of claim 19, wherein the sensitivity is in the range of 0.5×10 -3 cps/nv to 4.0 ×10 -3 cps/nv, and preferably is 2.5×10 -3 cps/nv.

Claim 23

The detector of claim 1, wherein at least one cable is disposed within the detector between the electrodes and the seal.

Claim 24

The detector of claim 1, wherein the cable insulation is in the form of microscopic spheres of silica compacted to approximately 35% volume fraction, this compaction providing for very fast gas migration through the cable, to thus eliminate the slow drifting in the detector signal which would result from use of normal mineral insulated cables such as alumina and magnesia.

Claim 25

The apparatus of claim 21, wherein the detector and integrally attached cables are substantially encased in insulators in the form of alumina cylinders.

Claim 26

The apparatus of claim 22, wherein the dry tube is backfilled with helium gas to permit lowering the detector anode temperature from approximately 1186° F. down to approximately 986° F.

Claim 27

The detector of claim 1, wherein the ratio of U-235 to U-234 is selected to provide a sensitivity versus neutron exposure relation which results in approximately a 60% reduction in sensitivity in five full power years.

Claim 28

The detector of claim 1, wherein the target sensitivity at the end of five full power years is selected to be 1×10 -3 counts per second/nv, such that an initial sensitivity of 2.5×10 -3 counts per second/nv is selected for the detector sensitivity.

Claim 29

The detector of claim 1, wherein the detector is designed to discriminate against any alpha signal emitted by the detector in the source range counting mode.

Claim 30

The detector of claim 1, wherein the detector is housed in a dry tube.

Claim 31

The detector of claim 1, wherein the detector is housed in a wet tube.

Claim 32

The detector of claim 1, wherein the detector and the cable are electrically isolated from reactor ground by means of coaxial ceramic insulators.

Claim 33

The detector of claim 1, wherein a triaxial assembly is provided in which an outer sheath is in contact with reactor ground, and an inner sheath is electrically isolated by the outer cable insulation and an insulating sleeve outside the detector

Claim 34

The apparatus of claim 21, wherein the cable contains a copper shield inside a stainless steel outer sheath, in order to minimize electromagnetic interference.

Claim 35

The detector of claim 1, wherein the detector is capable of measuring a neutron flux over a ten decade range.

Claim 36

The detector of claim 1, wherein the detector produces an output signal which is electrically separated to flow through a counting channel and a mean square voltage channel.

Claim 37

In combination with a nuclear reactor including a reactor core, a reactor vessel, a fixed site interior of said core for disposing a neutron sensor, cables running from said fixed site interior of said core to a location exterior of said pressure vessel, a power supply capable of delivering power exterior of said core, and a signal processor capable of analyzing electrical signals including current exterior of said core, the improvement of a wide range neutron detector connected across said cables comprising: (a) a sealed chamber, having first and second spaced electrodes positioned therein, disposed in said core having a neutron flux, with the first electrode connected to receive power from the power supply and the second electrode connected to deliver current to the signal processor through said cables, which chamber is hermetically sealed with a seal which is disposed exterior of said core within said vessel having a neutron flux which is substantially at least two decades below the neutron flux in the core location of the detector; (b) an ionizable gas, disposed within the space between the electrodes, pressurized to a pressure above one atmosphere; and (c) a layer of a mixture of an active material and a breeding material, positioned within the chamber, the active material and the breeding material being respectively U-235 and U-234, the layer having a thickness of at least 0.2 milligrams per square centimeter, which active material when struck by the neutron flux is capable of ionizing the gas to cause conduction of electric current from the first electrode through the second electrode to the signal processor, which current is proportional to the intensity of the neutron flux.

Claim 38

In combination with a nuclear reactor including a reactor core, a reactor vessel, a fixed site interior of said core for disposing a neutron sensor, cables running from said fixed site interior of said core to a location exterior of said pressure vessel, a power supply capable of delivering power exterior of said core, and a signal processor capable of analyzing electrical signals including current exterior of said core, the improvement of a wide range neutron detector connected across said cables comprising: (a) a sealed chamber, having first and second spaced electrodes positioned therein, disposed in said core having a neutron flux, with the first electrode connected to receive power from the power supply and the second electrode connected to deliver current to the signal processor through said cables, which chamber is hermetically sealed with a seal which is disposed exterior of said core within said vessel having a neutron flux which is substantially at least two decades below the neutron flux in the core location of the detector; (b) an ionizable gas, disposed within the space between the electrodes, pressurized to a pressure above one atmosphere; and (c) a layer of a mixture of an active material and a breeding material, positioned within the chamber, the active material and the breeding material being respectively U-235 and U-234, the layer having a thickness of at least 0.2 milligrams per square centimeter, which active material when struck by the neutron flux is capable of ionizing the gas to cause conduction of electric current from the first electrode through the second electrode to the signal processor, which current is proportional to the intensity of the neutron flux.

Claim 39

The detector of claim 1, wherein the detector and the cable are electrically connected to reactor ground.