USRE35908E - Neutron individual dose meter neutron dose rate meter, neutron detector and its method of manufacture - Google Patents

Neutron individual dose meter neutron dose rate meter, neutron detector and its method of manufacture Download PDF

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USRE35908E
USRE35908E US08/662,229 US66222996A USRE35908E US RE35908 E USRE35908 E US RE35908E US 66222996 A US66222996 A US 66222996A US RE35908 E USRE35908 E US RE35908E
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neutron
neutron detector
detection element
charged particles
neutrons
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Hiroshi Kitaguchi
Shigeru Izumi
Akihasa Kaihara
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Hitachi Ltd
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Hitachi Ltd
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    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00—Measuring neutron radiation
    • G01T3/08—Measuring neutron radiation with semiconductor detectors
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/02—Dosimeters
    • G01T1/026—Semiconductor dose-rate meters

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  • the present invention relates to a portable neutron dose meter for use by individuals who are engaged in radiation handling in radiation handling facilities such as nuclear power plants, reprocessing facilities and the like, a neutron exposure dose rate meter for monitoring neutrons within the compounds of neutron handling facilities, and a neutron detector which serves as their detection element, and more specifically it relates to such that employs a semiconductor detector as its neutron detection element.
  • the structure of the neutron detector in the prior art referred to in the former has a boron layer on the surface of the semiconductor detection element for detecting low energy thermal neutrons, and a polyethylene layer formed on the boron layer for detecting high energy fast neutrons. Further, in front of them, neutron moderator material is disposed to moderate neutron energy.
  • the neutron detector in the prior art referred to in the latter case has a boron layer formed on the surface of a semiconductor detection element likewise the former example, the periphery of which layer is further surrounded by neutron moderator material in order to detect fast neutrons.
  • the range of energy includes a region for thermal neutrons having energy in the thermal neutron region below 0.5 eV, to fast neutrons ranging above 0.5 eV up to 10 MeV.
  • a sensitivity curve with respect to each specific energy is called a response. Since the difference in the effective dose equivalent responses in terms of sensitivities between the thermal neutron region and the MeV region is as large as more than 50 times, it is extremely difficult to implement this required response. The required response will be called as a dose equivalent response hereinunder. In order to satisfy the dose equivalent response, it is important (1) to make the shapes of sensitivity curves to coincide with each other or minimize the difference in the sensitivities, and (2) to increase sensitivity to each energy.
  • the prior arts 1 and 2 have a structure such that a layer of boron 10( 10 B) is formed on the surface of a semiconductor detection element, and charged particles ( ⁇ rays) generated in the layer when neutrons enter therein are detected by the semiconductor detection element. Such materials which generate charged particles when thermal neutrons enter will be called a converter hereinafter.
  • the thickness of a boron 10 layer is formed to 1 micron m thickness by plasma doping techniques. Boron, however, has drawbacks that its melting point is as high as 2300 degree C., and its processibility is extremely poor.
  • the thickness of a boron film cannot be increased more than 1 micron m in order to prevent peel-off of the film due to temperature changes, because thermal expansion coefficients between boron and silicon which constitutes a semiconductor detection element differ as large as 3.5 times.
  • the number of ⁇ rays generated in boron being increased in proportion to its film thickness, there has been a problem in implementing a neutron detector which has a sufficient detection sensitivity. While in the prior art 1 there has been described diffusion injection means for injecting boron, it has not been successful in increasing boron concentrations in diffused layers, thus failing to attain a neutron detector having a sufficient detection sensitivity.
  • Such substance which generates protons when encountered with incident fast neutrons is called a proton radiator. It, however, has had a problem that it could not improve sensitivity to neutrons in an energy range from 10 KeV to 1 MeV.
  • a fist object of the present invention is to provide for a portable neutron individual dose meter which attains the dose equivalent response.
  • a second object of the present invention is to provide for a portable neutron individual dose meter which attains the dose equivalent response by using a single semiconductor detection element.
  • a third object of the present invention is to provide for a portable neutron individual dose meter which has a high sensitivity to thermal neutrons.
  • a fourth object of the present invention is to provide for a portable neutron individual dose meter which has a high sensitivity to fast neutrons.
  • a fifth object of the present invention is to provide for a neutron exposure dose rate meter which implements the dose equivalent response.
  • a neutron detector having a layer comprising a first material which emits charged particles through a nuclear reaction with incident thermal neutrons and a second material which emits charged particles through interactions with incident fast neutrons, the same layer being bonded on the surface of a semiconductor detection element; a processing circuit for processing signals obtained from the neutron detector, and a power source for supplying power to the neutron detector and the processing circuit.
  • a neutron detector having a grain-formed material which emits charged particles through a nuclear reaction with incident thermal neutrons and another material which does not emit charged particles through interactions with incident fast neutrons, each being formed on the surface of a semiconductor detection element; a processing circuit for processing signals obtained from the neutron detector; and a power source for supplying power to the neutron detector and the processing circuit.
  • a single semiconductor wafer a pair of electrodes formed on the obverse and reverse surfaces of the semiconductor wafer; a power source for supplying power to the electrodes; a neutron detector having a semiconductor detection element wherein the electrode through which the charged particles enter is formed so as to cover a portion of a depletion region thereof; a processing circuit for processing signals obtained from the neutron detector; and a power source for supplying power to the neutron detector and the processing circuit.
  • a neutron detector having a layer comprising a first material which emits charged particles through a nuclear reaction with incident thermal neutrons and a second material which emits charged particles through interactions with incident fast neutrons, the same layer being formed on the surface of a semiconductor detection element; at least one of a neutron moderator and a thermal neutron absorber which are installed in the direction of the incident neutrons with respect to, or in such a manner as to surround, the neutron detector; a processing circuit for processing signals obtained from the neutron detector; and a power source for supplying power to the neutron detector and the processing circuit.
  • a neutron detector having a layer comprising a first material which emits charged particles through a nuclear reaction with incident thermal neutrons and a second materials which emits charged particles through interactions with incident fast neutrons, the layer being formed on the surface of a semiconductor detection element; a phantom which simulates a human body on which to attach the neutron detector; a processing circuit for processing signals obtained from the neutron detector; and a power source for supplying power to the neutron detector and the processing circuit.
  • a neutron detector having a material bonded on its surface, which emits charged particles through interactions with incident neutrons; a neutron moderator and a thermal neutron absorber disposed such as to surround the neutron detector; a processing circuit for processing signals obtained from the neutron detector; and a power source for supplying power to the neutron detector and the processing circuit.
  • the dose equivalent response Sa(E) is capable of being expressed by equation 1 as follows.
  • Da(E) represents a neutron sensitivity response, indicating a sensitivity response to neutron energy E by the neutron detector itself
  • fa(e) represents a phantom sensitivity response, indicating a response to the neutron detector of incident neutrons entering a human body or human body simulator
  • Ia(E) indicates an incident neutron spectrum
  • the neutron sensitivity response Da (E) indicates a preferred response D(E)
  • the human body itself indicates a preferred phantom response D(E) of necessity.
  • the effective dose equivalent response S(E) it is necessary for the effective dose equivalent response S(E) to be satisfied at least by the product of responses of the neutron detector and a human body simulating phantom. Namely, if the neutron detector satisfies the effective dose equivalent response D(E) by itself, the phantom may be constituted simply to simulate a human body.
  • the phantom may be constituted, though a total sensitivity may drop, to complement the insufficiency so as to satisfy the effective dose equivalent response S(E) as a whole.
  • the neutron sensitivity response D(E) involves roughly two curves, this is based on the knowledge that; a first curve, D 1 (E) depends on a converter which emits low energy neutrons consisting mainly of thermal neutrons and ⁇ rays; and a second curve D(2)(E) depends on a proton radiator which emits protons through interactions with high energy neutrons consisting mainly of fast neutrons. Thereby, it is not necessary to provide the neutron moderator disposed in front of the neutron detector as described in the prior art 1.
  • the converter and the proton radiator are provided in separate layers, for example, in the sequence of a converter directly on a semiconductor detection element, then a proton radiator thereupon, protons generated in the proton radiator cannot reach the semiconductor detection element being prevented by the converter.
  • the converter and proton radiator are provided in the same composite layer each coexisting therein, bonded to the surface of a semiconductor detection element.
  • the neutron sensitivity response D(E) is capable of being satisfied by adjusting respective amounts of the converter and proton radiator, and a total thickness of the layer.
  • the response of a semiconductor neutron detection element having a converter and a proton radiator varies greatly according to its structure how the converter and proton radiator are built.
  • An increased sensitivity to thermal neutrons is capable of being attained by increasing the thickness of a converter, i.e., the thickness of a boron layer.
  • Boron has such drawbacks that it has a melting point as high as approximately 2300° C., an extremely poor processibility, and that the difference in thermal expansion coefficients between a boron film and silicon constituting a semiconductor detection element is as large as 3.5 times, thus failing to provide a boron film having a thickness more than 1 ⁇ m.
  • an effective thickness of a film is enabled to be increased by providing boron in a grain form or powder mixed with other materials.
  • These other materials are preferably such that which has a thermal expansion coefficient not too much different from that of silicon, or that which has elasticity so as to absorb the thermal expansion of boron.
  • boron is prepared in grain, and a boron layer is formed by calcination of grain boron, its processibility will be much simplified.
  • the boron layer is composed of grain boron, a peel-off problem of the layer due to the difference in the thermal expansion coefficients with silicon caused by temperature changes is solved.
  • a sufficiently thicker boron layer than by the prior art is capable of being formed, providing for an increased sensitivity to thermal neutrons.
  • the other material of the above is a hydride compound to be utilized as the proton radiator
  • its grain size (average grain diameter) of boron it is possible to control the quantity of the hydride compound to be bonded to the surface of silicon.
  • the sensitivity to fast neutrons being changed accordingly, the response characteristics of the detector are capable of being adjusted with respect to a total neutron energy, which is also preferable in implementing the effective dose equivalent response.
  • the hydride compounds are preferable in view of mitigating the peel-off problem.
  • a grain size of the grain converters is likely to control a total response.
  • ⁇ rays of 1.47 MeV will be produced through a nuclear reaction with thermal neutrons.
  • proton radiators will produce proton beams through interactions with fast neutrons.
  • pairs of charges of electrons and holes are generated therein through the charged particles' ionization actions. Since a range for ⁇ rays is less than 10 ⁇ m, a thickness more than that for the converters will make no difference in sensitivity responses.
  • a range for proton rays emitted from the proton radiators is approximately 1 mm at an energy level of 10 MeV.
  • neutron dosimeters for personal use have to be portable, such a structure surrounded in a neutron absorber of a large dimension as in the neutron dose rate meter will not be advantageous in practical applications.
  • the human body When a personal dosimeter is used fixed to the chest of a human body, the human body itself serves as a neutron moderator. That is, fast neutrons are scattered and moderated in the human body, and the scattered components which are typically caleed albedo neutrons are effected to enter the dosimeter.
  • a neutron dosimeter for personal use having the dose equivalent response is capable of being implemented.
  • a neutron dose rate meter which satisfies the effective dose equivalent response S(E), simply by attaching a neutron exposure dosimeter for personal use on the phantom which simulates a human body.
  • a neutron exposure dosimeter for personal use on the phantom which simulates a human body.
  • a phantom there is water, acrylic, or the like.
  • neutron moderators or thermal neutron absorbers are substituted for the phantom.
  • the semiconductor detection element may be surrounded by neutron moderators or thermal neutron absorbers. Then, by increasing the thickness of the neutron moderator, it is possible to adjust a rate of sensitivity, i.e., decreasing the sensitivity to thermal neutrons and increasing that to fast neutrons.
  • thermal neutron absorbers or the width of openings are adjusted.
  • a thermal neutron absorber with openings is fully transparent to fast neutrons permitting then to transmit therethrough.
  • Sensitivity to thermal neutrons is capable of being adjusted by controlling in opening ratio. Through such arrangement, sensitivity to each energy source is capable of being adjusted, hence providing for a phantom which simulates human body.
  • any neutron detectors consisting of semiconductor detection elements without utilizing silicon may be also employed.
  • FIG. 1 shows a neutron individual exposure dosimeter according to a first embodiment of the present invention.
  • FIG. 2 shows an effective dose equivalent response, the response of a neutron detector, and the response of a phantom, relative to incident energy spectra.
  • FIG. 3 illustrates how an individual neutron dosimeter according to the present invention is attached to the body.
  • FIG. 4 shows a schematic diagram of a semiconductor neutron detector and a block diagram of a measurement circuit for the neutron individual dosimeter.
  • FIG. 5 shows a relationship between the number of nuclear reactions N(I) and the thickness of converters.
  • FIG. 6 shows the result of comparison of responses between the neutron individual dosimeter according to the present invention and the effective dose equivalent.
  • FIG. 7 illustrates a state at calibration of the personal dosimeter of the present invention.
  • FIG. 8 shows a personal neutron dosimeter of a second embodiment of the invention.
  • FIG. 9 shows a personal neutron dosimeter of a third embodiment of the invention.
  • FIG. 10 shows a personal neutron dosimeter of a fourth embodiment of the invention.
  • FIG. 11 shows a neutron dose rate meter of a first embodiment of the present invention.
  • FIG. 12 is a schematic diagram illustrating a neutron detector portion of a first embodiment of the invention.
  • FIG. 13 shows a structure of a neutron detector and a block diagram of a radiation measurement circuit 60.
  • FIG. 14 shows energy responses of the neutron dosimeters according to the present invention, when the thickness of neutron moderators was varied.
  • FIG. 15 shows the result of comparison of the responses between the neutron dosimeters of the present invention and the effective dose equivalent.
  • FIG. 16 shows a neutron dose rate meter of a second embodiment of the present invention.
  • FIG. 17 shows directivity in a perpendicular direction for the neutron dose rate meter of the second embodiment of the invention.
  • FIG. 18 shows a neutron dose rate meter of another embodiment of the invention.
  • FIG. 19 is a cross-sectional view of the embodiment of FIG. 18.
  • FIG. 20 shows a neutron dose rate meter of still another embodiment of the invention.
  • FIG. 21 shows a neutron dose rate meter of furthermore embodiment of the invention wherein a thermal neutron absorber is included inside a neutron moderator.
  • FIG. 22 shows a neutron dose rate meter of still further embodiment of the invention wherein a thermal neutron absorber is disposed in a space inside a neutron moderator.
  • FIG. 23 illustrates an exemplary distribution of wave heights of signals measured according to the present invention.
  • FIG. 1 shows a personal semiconductor neutron dosimeter of a preferred embodiment of the present invention.
  • a semiconductor neutron detection element 1; a radiation measurement circuit (hybrid circuits) 33 including a preamplifier, a discriminator, a reverse bias application circuit and the like; an arithmetic display unit 34; and a power source 35 are contained in a portable carrying case 32.
  • This portable dosimeter is attached to the chest portion of a worker with a clip 36.
  • FIG. 3 illustrates how this semiconductor neutron dosimeter 32 is attached to a human body 31.
  • FIG. 4 shows the structure of a semiconductor detection element, and a block diagram of the measurement circuit for a personal neutron dosimeter.
  • the structure of a semiconductor detection element 1 will be described by using n-type silicon as an example.
  • p-n junction (p-layer) 8 is formed in the surface of n-type silicon 1 through impurity (boron) diffusion.
  • the surface of the junction 8 is then insulated and protected by a silicon oxide film (SiO 2 ).
  • a pointed junction electrode 10 for loading out signals is provided as shown in the figure, and an earth electrode 11 provided in ohmic contact on the surface opposite the junction is led out.
  • a reverse bias voltage is applied between the electrodes 10 and 11, a depletion region 7 is effected to expand below the junction 8.
  • a mass of grain (powder) shaped boron 5 is bonded tightly by calcination.
  • the interstices between the grains are infiltrated by proton radiators (hydride compounds) and the outer surface thereof is further covered by the same 6.
  • hydride compounds there are paraffin, epoxy, polyethylene or the like.
  • the whole detection element is hermetically sealed in a can, though not shown, and lead wires from respective electrodes at p-layer 8 and n-layer 4 are drawn outside the can.
  • the electrode 10 in contact with the p layer 8 is formed into a point in order to prevent attenuation of ⁇ rays and protons.
  • the oxide film 9 which serves as an incident window for ⁇ rays and the like is readily formed into a thickness of approximately 100 ⁇ .
  • neutron moderator (not shown) is required to be used outside or inside the sealing can.
  • Incident thermal neutrons(Nth) incoming from outside into a dosimeter of the present invention enter into a nuclear reaction in thermal neutron converter 5 to generate ⁇ rays.
  • fast neutrons (Nf) generate repulsion protons through scattering actions with proton radiators.
  • ⁇ rays and proton rays produce electric charges in the depletion region 7 in the detection element 1.
  • Such electric charges produced in accordance with the incident thermal neutrons (Nth) and fast neutrons (Nf), after being guided through ac coupling capacitance 13, are amplified in a preamplifier 14 and a linear amplifier 15, respectively.
  • Amplified signals undergo wave height discrimination in a discriminator 16, and their pulses are measured in a counter circuit 17. Based on the values counted in the counter circuit 17, quantities of dose are calculated and displayed in an arithmetic/display unit 18.
  • the principle of neutron detection according to the present invention is roughly classified into two categories as follows.
  • One is that low energy thermal neutrons enter into a nuclear reaction in boron 5 as represented by equation 3, hence emitting ⁇ rays therefrom.
  • ⁇ rays have energy of 1.47 MeV, and produce charges of pairs of electrons e and holes h in the depletion region 7 in the detection element 1, which charges cause to vary the detector current.
  • incident fast neutrons interact (scatter) with proton radiators 6, generating repulsion protons, which in turn produce charges of pairs of electrons e and holes h in the depletion region 7, which cause to vary the detector current.
  • the preferred embodiment of the invention described herewith is capable of providing an improved detection sensitivity and a wider range of energy detection through improving probabilities of occurrence of respective interactions according to the above two categories, and efficiencies of collecting introduced charged particles ( ⁇ rays, protons). The details of their operations will be described below.
  • N (l) of nuclear reactions taking place in boron 5 which serves as a converter is expressed as follows.
  • n atomic density of converter (1/cm 3 )
  • the number N(l) of nuclear reactions is directly proportional to the thickness 1 of the converter, which numeric relationship is shown in FIG. 5.
  • the flight range in boron and silicon of ⁇ rays generated in the converters is up to 7 ⁇ m.
  • an occurrence probability ⁇ p of protons to be generated by fast neutrons by scattering in the proton radiator 6 will be expressed by the following equation, wherein an incident energy of neutrons is given by En(MeV). ##EQU1## Namely, the occurrence probability ⁇ p changes in proportion to the power of -1/2 of incident neutron energy En, which occurrence probability, however, does not depend on the scattering angle of protons.
  • the energy of the protons hereinabove generated depends on scattering angles, thereby, an energy distribution for protons generated by monochrome neutrons involves a continuous distribution from 0 eV energy up to incident energy En. The range of the protons is approximately 1 mm at 10 MeV, but low energy protons are rapidly attenuated while passing through boron.
  • a layer thickness 1c composed of grain boron 5 easy to process having an average in size of 10 ⁇ m is set at 30 ⁇ m with a porosity rate of 75%, which corresponds to a layer thickness of 7 ⁇ m consisting of 100% boron, so that a calcinated layer thickness as thick as possible to maximize the number N(l) of nuclear reactions without exceeding the range of ⁇ rays may be obtained.
  • ⁇ rays generated in the grain shaped boron 5 have energy of 1.47 MeV, thereby they are scarcely attenuated while passing through several ⁇ m of proton radiators composed of hydride compounds having a small atomic number. Further, on the side of the semiconductor detection element 1, the oxide film 9 and p-layer 8 being insensitive to charged particles, and only causing attenuation to ⁇ rays and the like, their thickness is controlled within 0.3 ⁇ m in order to prevent drop of sensitivity.
  • the present embodiment of the invention has advantages as follows simply as a personal neutron dosimeter. Because of an increased effective thickness of boron enabled by being provided in grain form, detection sensitivity to thermal neutron is capable of being improved approximately by 10 times greater than the prior arts. Further, the shield effect of boron on fast neutrons, in particular, on the fast neutrons in lower energy side is capable of being reduced, thereby, detection sensitivity for fast neutrons is capable of being improved as a whole. Still further, with respect to the manufacturing techniques, there are no specific problems, and calcination (evaporation solidification) of grain boron is readily performed.
  • permeable coating using permeable hydride compounds is effective for preventing reduction in a boron layer by peel-off due to temperature changes.
  • a composite layer comprising boron and proton radiators may be fixed to a semiconductor element with a plastic fixing film.
  • a pointed electrode provided in the side of the charged particle converter such as boron and the like, a portion of the electrode which blocks the passage of charged particles into the semiconductor detection element is capable of being eliminated.
  • the oxide film 9 is capable of being made thinner. Thereby, transmissivity of charged particles into the semiconductor detection element is capable of being substantially improved, thus increasing the detection sensitivity over a wider range of neutron energy.
  • the detection sensitivity to fast neutrons is capable of being adjusted by changing the coating layer thickness 1p of the proton radiator 6, the particle size of the grain boron 5, or a ratio of quantities between the proton radiator and the grain boron.
  • a solid line curve in FIG. 4 A solid line curve in FIG.
  • FIG. 6 shows a relationship between the neutron energy and the effective dose equivalent (which indicates degrees of influence upon human body) according to the ICRP recommendation. Circles o in the figure indicate characteristics of the embodiments of the present invention, while x marks indicate those of the prior art detectors. Data available in FIG. 6 are limited in the range of thermal neutron, and from several 100 KeV up to 15 MeV. Data between several 100 KeV and thermal neutrons are interpolated by Monte Carlo simulation. This is because that data in such intermediate region cannot be gathered experimentally by the present state-of-the-art technologies.
  • FIG. 6 shows the behavior of a neutron in a phantom simulating a human body. A part of fast neutrons interacts with proton radiators in the dosimeter, but most of them reaches a phantom 30 and are scattered therein. Some of the scattered beams enter a neutron detection element 1.
  • the energy of neutrons which enter the dosimeter includes, with the incident neutrons being the maximum, up to thermal neutrons. It is possible readily to obtain the response of the effective dose equivalent by adjusting the kinds of converters in the dosimeter, its grain size, layer thickness, and also the kinds of proton radiators and its layer thickness.
  • charged particles are generated through such a structure that grains of boron are calcinated, and their interstices and a surface thereon are plugged with proton radiators.
  • Such structure may be substituted for with a compound or mixture of boron and hydride compounds.
  • FIG. 8 Another neutron detector of a second embodiment of the present invention will be described below with reference to FIG. 8.
  • This embodiment has such a structure that a boron plate 50 having openings is provided in the surface of a semiconductor detection element 1, and the openings are plugged with proton radiators 51.
  • it is possible to adjust the response of the detector by adjusting the area of openings (in case the opening is a circle, its diameter).
  • a method of manufacturing boron plates having arbitrary shapes and openings may be implemented, first by forming a boron layer in front of a metal mask using sputtering techniques or the like, then removing the metal mask.
  • the boron plate prepared as above is attached firmly on the surface of a semiconductor detection element 1. Attachment may be accomplished simply by bonding using adhesives or with mechanical fixture at peripheral portions.
  • FIG. 9 a third embodiment of the invention is shown in FIG. 9.
  • This embodiment consists of a semiconductor detection element 1 and a proton radiator 53 formed thereon, thus providing a detector which is sensitive only to fast neutrons.
  • the proton radiator 53 is capable of being provided simply by applying paraffin or the like as in the case of FIG. 4. According to this embodiment of the invention, it is capable of providing a personal neutron dosimeter which has an especially high detection sensitivity to fast neutrons.
  • FIG. 10 A fourth embodiment of the invention is shown in FIG. 10.
  • a layer of grains of boron 55 is formed on the surface of a semiconductor detection element 1, an outer surface of which is coated by substance devoid of hydrogen such as aluminum evaporation film 56 for protection.
  • This detector prepared as above is sensitive only to thermal neutrons, and a peel-off problem due to temperature changes is minimized through the employment of grains of boron with a maximized thickness permitted for the layer, thus substantially having improved detection sensitivity to thermal neutrons.
  • Boron is utilized as material for effecting nuclear reactions with thermal neutrons in each of the above embodiments of the invention.
  • This may be replaced by lithium effecting a nuclear reaction of 6 Li(n, ⁇ ) 3 H, or by uranium.
  • energy of ⁇ rays emitted therefrom differs from that of boron, it is necessary to determine the thickness of converters appropriately according to their flight ranges.
  • proton radiators such as hydride compounds or the like, which, however, may be any other substance only if it generates heavy charged particles through interactions with fast neutrons.
  • silicon semiconductors utilized for semiconductor detection elements in the above description may be replaced by chemical compound semiconductors using cadmium telluride, mercury iodide or the like.
  • FIG. 11 shows a semiconductor neutron dose rate meter of an embodiment of the invention.
  • a human body simulating phantom is composed of a spherical neutron moderator 2 and a thermal neutron absorber 3 which have openings, the latter disposed over the outer shell.
  • the above semiconductor neutron detector 40 is installed inside the phantom. Neutron detection signals are transmitted outside to a radiation measurement circuit 60 via a signal cable.
  • This type of system using the spherical neutron moderator 2 is capable of providing a preferable dose rate meter which retains a maximized nondirectivity.
  • FIG. 12 illustrates a schematic diagram of a neutron detection portion according to the present invention.
  • a semiconductor detector as shown in FIG. 4 is installed at the center of a neutron moderator 2 made of paraffin or polyethylene, and a thermal neutron absorber 3 made of cadmium plate or the like having openings.
  • a metal case (can) for hermetically sealing in a semiconductor detection element 1 and a signal cable for taking out signals are omitted.
  • Incident thermal neutrons(Nth) entering the dose rate meter from outside are partially absorbed in the thermal neutron absorber 3 and neutron moderator 2, and a portion of which reaches the detection element 1.
  • FIG. 13 shows a neutron detector structure and a block diagram of a radiation measuring circuit 60.
  • the radiation measuring circuit 60 is basically the same as that in FIG. 4, but has two types of discriminators 16 and counter circuits 17, respectively.
  • Suffix a subsystem represents an energy dependent total counter, while suffix b sub-system indicates a circuit for discriminating fast neutrons having energies greater than a prescribed value to be described later.
  • FIG. 14 shows examples of measurements of energy responses by the neutron dose rate meter of the invention. This figure shows the results of measurements obtained by varying the thickness of the neutron moderator as a parameter. Main specifications of the structure of this neutron dose rate meter is as follows.
  • FIG. 15 shows the response of the neutron dose rate meter according to the present invention in comparison with the response of the effective dose equivalent.
  • the thickness of the neutron moderator was 80 mm (the same data as for the moderator thickness of 80 mm in FIG. 14). The data was interpolated likewise that in FIG. 6.
  • the response of the neutron dose rate meter of the invention.Iadd. as shown by the circles o substantially lying the solid line curve, .Iaddend.agrees well with the dose equivalent response at a high precision within ⁇ 30% over an energy range from the thermal neutrons up to 15 MeV.
  • some examples of the response of a prior art dose rate meter are shown.
  • the prior art dose rate meter.Iadd. as shown by x marks connected by the one-dot chain line curve, .Iaddend.has shown that its sensitivity falls exceeding several MeV.
  • the neutron radiation dose rate meter is capable of being applied to an area monitor, environmental monitor, surveillance monitor and so on to be employed for radiation handling facilities such as nuclear power generation plants or the like, thus providing a novel and practical measuring device.
  • FIG. 16 Still another neutron radiation dose rate meter of a second embodiment of the invention is shown in FIG. 16.
  • a neutron radiation moderator of a nearly spherical body more specifically, a right circular cylinder body having the same length for the diameter and the height, is utilized.
  • a semiconductor neutron detector 40 is placed in the center of the neutron radiation moderator 2, over the outer surface of which thermal neutron absorbers 3 having openings are attached.
  • Neutron detection signals are transmitted, via a signal cable, to a measurement circuitry 60 and an indicator unit 20 which includes a data processing unit.
  • a neutron radiation moderator 2 having an outer form of a sphere is expensive to manufacture.
  • FIG. 17 shows the result of the investigation on the directivity obtained in a perpendicular direction and other incident angles with respect to this embodiment.
  • the directivity is capable of being ignored within an allowance of ⁇ 10%. This is because of the effect of a repeated scattering of the neutrons within the moderator so as to permit the directivity to be lessened substantially.
  • FIG. 18 illustrates a neutron moderator 2 of the invention shaped into a square cube, every corner of which is cut out.
  • FIG. 19 shows a raised plan view of FIG. 18.
  • a neutron detector 40 is disposed in the center in each of these embodiments described herewith.
  • FIG. 20 is still another modification of the neutron moderator 2 of the invention formed into a right circular cylinder the corner of which to be cut away likewise.
  • FIGS. 18, 19 and 20 illustrations of a thermal neutron absorber 3 are omitted.
  • FIG. 21 shows a thermal neutron absorber 3 disposed in another modified version of the invention.
  • the thermal neutron absorber 3 having openings is installed inside a neutron moderator 2.
  • FIG. 22 shows another thermal neutron absorber 3 disposed in still another modified version of the invention, wherein a thermal neutron absorber 3 having openings is disposed in an interstice between a neutron moderator 2 and a neutron detector 40.
  • the thermal neutron absorber 3 is disposed deeper inside the neutron moderator 2, the quantity of the thermal neutron absorber 3 is capable of being reduced.
  • FIG. 23 shows an example of the wave height distribution (spectrum) of signals measured according to the present invention.
  • ⁇ region between the wave height values A and B represents a wave height region for ⁇ rays generated by the nuclear reactions with thermal neutrons.
  • the region exceeding wave height value B represents a wave height region for protons generated through interactions with fast neutrons having several MeV.
  • a region below wave height B indicates wave height values for gamma rays.
  • thermal neutron absorber boron or lithium is capable of being substituted for cadmium.
  • the detection sensitivity to thermal neutron components is adjusted by changing the opening ratio in the neutron absorber, it is, however, possible to effect the sensitivity adjustment by changing the thickness of the thermal neutron absorber.
  • semiconductor detection elements are utilized as detection elements in the above embodiments as in the case of the personal dosimeter, chemical compound semiconductors such as cadmium telluride or mercury iodide may be utilized instead.
  • a neutron dose rate meter is capable of being provided which is capable of implementing the effective dose equivalent response, through installing a neutron detector capable of implementing the effective dose response on a certain volume of water, acrylic or the like serving as a phantom simulating a human body, which has been described in the personal dosimeter using neutron moderators and thermal neutron absorbers.
  • the neutron detectors are limited to such that are capable of attaining the effective dose equivalent response.
  • the dose equivalent response is capable of being changed by varying the thickness of the neutron moderators or thermal neutron absorbers as well.
  • a neutron detector cannot realize the effective dose equivalent response by itself, it is still possible to implement the effective dose equivalent response as a whole of a neutron dose rate meter by changing the thickness or the like of the neutron moderator or thermal neutron absorber which surround the same neutron detector.
  • the neutron detector may be a BF 3 counter or 3 He counter.
  • the neutron moderators and thermal neutron absorbers are disposed in enclosure In such a case, however, when a neutron dose rate meter is disposed along a wall, because an incident direction of neutron radiations is limited, the neutron moderator or thermal neutron absorber may be installed only in such a specific incident direction.
  • the present invention is capable of providing a personal neutron dosimeter which implements the dose equivalent response.

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US08/662,229 1990-04-24 1991-04-26 Neutron individual dose meter neutron dose rate meter, neutron detector and its method of manufacture Expired - Lifetime USRE35908E (en)

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JP11009290 1990-04-27
JP2-110092 1990-04-27
PCT/JP1991/000574 WO1991017462A1 (fr) 1990-04-27 1991-04-26 Dosimetre d'exposition aux neutrons pour utilisation individuelle, debitmetre de dose de neutrons, detecteur de neutrons et procede pour leur fabrication
US07/778,876 US5321269A (en) 1990-04-24 1991-04-26 Neutron individual dose meter, neutron dose rate meter, neutron detector and its method of manufacture
US08/662,229 USRE35908E (en) 1990-04-24 1991-04-26 Neutron individual dose meter neutron dose rate meter, neutron detector and its method of manufacture

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Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1386485A (fr) * 1963-12-13 1965-01-22 Radiotechnique Dispositif à semi-conducteur pour la détection et le comptage de neutrons
US4074136A (en) * 1974-10-08 1978-02-14 Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung Apparatus for determining the dose equivalent of neutrons
JPS5595886A (en) * 1979-01-17 1980-07-21 Tdk Corp Neutron detector
JPS5595868A (en) * 1978-10-13 1980-07-21 Sun Tech Inc Determination of critical melting temperature of perfluorocarbon
JPS58167988A (ja) * 1982-03-30 1983-10-04 Solar Optical Japan Kk 熱中性子測定用固体飛跡検出器素材
US4489315A (en) * 1982-03-03 1984-12-18 The United States Of America As Represented By The United States Department Of Energy Personnel electronic neutron dosimeter
JPH01164071A (ja) * 1987-12-21 1989-06-28 Fuji Electric Corp Res & Dev Ltd 半導体中性子線検出素子の製造方法
JPH01253971A (ja) * 1988-04-01 1989-10-11 Matsushita Electric Ind Co Ltd 半導体放射線検出器およびその製造方法

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3227876A (en) * 1956-12-03 1966-01-04 Hoffman Electronics Corp Neutron detecting solid state device or the like
JPS5080284A (enrdf_load_stackoverflow) * 1973-11-19 1975-06-30
JPS6068488U (ja) * 1983-10-19 1985-05-15 三菱原子力工業株式会社 中速中性子用モニタ
JPS6128885A (ja) * 1984-07-19 1986-02-08 Shoji Nakamura 中性子線検出器のフイルタの最適化方法
JPH0716024B2 (ja) * 1987-08-06 1995-02-22 富士電機株式会社 半導体放射線検出素子の製造方法
JPH0616112B2 (ja) * 1989-02-06 1994-03-02 尚司 中村 中性子個人被曝線量計

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1386485A (fr) * 1963-12-13 1965-01-22 Radiotechnique Dispositif à semi-conducteur pour la détection et le comptage de neutrons
US4074136A (en) * 1974-10-08 1978-02-14 Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung Apparatus for determining the dose equivalent of neutrons
JPS5595868A (en) * 1978-10-13 1980-07-21 Sun Tech Inc Determination of critical melting temperature of perfluorocarbon
JPS5595886A (en) * 1979-01-17 1980-07-21 Tdk Corp Neutron detector
US4489315A (en) * 1982-03-03 1984-12-18 The United States Of America As Represented By The United States Department Of Energy Personnel electronic neutron dosimeter
JPS58167988A (ja) * 1982-03-30 1983-10-04 Solar Optical Japan Kk 熱中性子測定用固体飛跡検出器素材
JPH01164071A (ja) * 1987-12-21 1989-06-28 Fuji Electric Corp Res & Dev Ltd 半導体中性子線検出素子の製造方法
JPH01253971A (ja) * 1988-04-01 1989-10-11 Matsushita Electric Ind Co Ltd 半導体放射線検出器およびその製造方法

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
Dale E. Hankins, "Phantoms for Calibrating Albedo Neutron Dosimeters." Health Physics, vol. 39, No. 3 pp. 580-584, Pergamon Press Ltd. Sep. 1980.
Dale E. Hankins, Phantoms for Calibrating Albedo Neutron Dosimeters. Health Physics , vol. 39, No. 3 pp. 580 584, Pergamon Press Ltd. Sep. 1980. *

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US20040188677A1 (en) * 2001-07-09 2004-09-30 Marlies Luszik-Bhadra Method and device for determining the personal dose in mixed neutron/photon fields
US7208743B2 (en) * 2001-07-09 2007-04-24 Bundesrepublik Deutschland, vertreten durch das Bundesministerium für Wirtschaft und Arbeit, dieses wiederum vertreten durch den Präsidenten der Physikalisch-Technischen Bundesanstalt Method and device for determining the personal dose in mixed neutron/photon fields
US20050258372A1 (en) * 2002-10-29 2005-11-24 Mcgregor Douglas S High-efficiency neutron detectors and methods of making same
WO2004040332A3 (en) * 2002-10-29 2004-10-07 Univ Michigan High-efficiency neutron detectors and methods of making same
US7164138B2 (en) 2002-10-29 2007-01-16 The Regents Of The University Of Michigan High-efficiency neutron detectors and methods of making same
US20040225134A1 (en) * 2003-05-09 2004-11-11 The Regents Of The University Of Michigan Implementation of a strategy for achieving extraordinary levels of surface area and porosity in crystals
US7652132B2 (en) 2003-05-09 2010-01-26 The Regents Of The University Of Michigan Implementation of a strategy for achieving extraordinary levels of surface area and porosity in crystals
US6930311B1 (en) 2003-05-21 2005-08-16 The United States Of America As Represented By The Secretary Of The Navy Lightweight neutron remmeter
US20050017185A1 (en) * 2003-07-01 2005-01-27 King Douglas Beverley Stevenson Radiation detector
US20050124819A1 (en) * 2003-12-05 2005-06-09 The Regents Of The University Of Michigan Metal-organic polyhedra
US7655921B2 (en) 2004-04-22 2010-02-02 Gsi Helmholtzzentrum Fur Schwerionenforschung Gmbh Dosimeter for the detection of neutron radiation
US20090039279A1 (en) * 2004-04-22 2009-02-12 Gsi Gesellschaft Fur Schwerionenforschung Mbh Dosimeter for the detection of neutron radiation
WO2005106532A3 (de) * 2004-04-22 2006-04-20 Schwerionenforsch Gmbh Dosimeter zur erfassung von neutronenstrahlung
US7582798B2 (en) 2004-10-22 2009-09-01 The Regents Of The University Of Michigan Covalently linked organic frameworks and polyhedra
US20060252641A1 (en) * 2005-04-07 2006-11-09 Yaghi Omar M High gas adsorption in a microporous metal-organic framework with open-metal sites
US7662746B2 (en) 2005-04-07 2010-02-16 The Regents Of The University Of Michigan High gas adsorption metal-organic framework
EP1729149A1 (en) * 2005-05-30 2006-12-06 Deutsches Elektronen-Synchrotron DESY Solid state neutron detector system
US20070068389A1 (en) * 2005-09-26 2007-03-29 Yaghi Omar M Metal-organic frameworks with exceptionally high capacity for storage of carbon dioxide at room-temperature
US7799120B2 (en) 2005-09-26 2010-09-21 The Regents Of The University Of Michigan Metal-organic frameworks with exceptionally high capacity for storage of carbon dioxide at room-temperature
US20070202038A1 (en) * 2006-02-28 2007-08-30 The Regents Of The University Of Michigan Preparation of functionalized zeolitic frameworks
US8314245B2 (en) 2006-02-28 2012-11-20 The Regents Of The University Of Michigan Preparation of functionalized zeolitic frameworks
US8809546B2 (en) 2006-02-28 2014-08-19 The Regents Of The University Of California Preparation of functionalized zeolitic frameworks
US20090302231A1 (en) * 2006-03-16 2009-12-10 Kansas State University Research Foundation Non-streaming high-efficiency perforated semiconductor neutron detectors, methods of making same and measuring wand and detector modules utilzing same
US7855372B2 (en) 2006-03-16 2010-12-21 Kansas State University Research Foundation Non-streaming high-efficiency perforated semiconductor neutron detectors, methods of making same and measuring wand and detector modules utilizing same
DE102014210944A1 (de) * 2014-06-06 2015-12-17 Berthold Technologies Gmbh & Co. Kg Messgerät zur Messung der Neutronendosis

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US5321269A (en) 1994-06-14
WO1991017462A1 (fr) 1991-11-14
JP2000147129A (ja) 2000-05-26
JP3140052B2 (ja) 2001-03-05
DE4190941T (enrdf_load_stackoverflow) 1992-04-23
DE4190941C2 (de) 2001-07-26

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