Patent Application
20130322587
The present invention relates to a tritium removal device for removing hydrogen and tritium, being an isotopic element thereof, which are generated on a lithium target to be applied as a neutron source, from a lithium loop, in which lithium flows=circularly, for example, in a boron neutron capture therapy (BNCT), which is applied for the purpose of a cancer medical treatment.
The boron neutron capture therapy (BNCT) is a medical treatment achieved for the purpose, i.e., selectively killing cancer cells, by “a” rays (helium nucleus) and secondary particle radiation of lithium nucleus (7Li), which are generated through neutron capture nuclear reaction from 10B of a boron isotope (10B) compound having a large neutron capture cross section, which is introduced into the cancer cells in advance, by irradiating thermal neutrons having relatively low energy, such as, equal to 0.5 eV or less than that, upon the cancer cells. Because a range of the “α” rays and so on is very short, only the cells taking 10B therein are destroyed, and therefore this attracts attentions as a medical treatment against the cancer, producing less unfavorable side effects.
In an initial boron neutron capture therapy (BNCT), there are used the neutrons from a nuclear reactor through deceleration thereof; however, at present, there are two types, i.e., applying the neutrons, which are generated by irradiation of protons accelerated through an accelerator upon solid Be cooled with water,=and also applying the neutrons, which are generated by irradiation of protons accelerated through an accelerator upon liquid lithium. Herein, explanation will be given on the latter, i.e., the method of applying the neutrons, which are generated by irradiating the protons upon the liquid lithium.
The method applying the liquid lithium therein as a target material has advantages that it enables to remove heats, continuously, by circulating the lithium, and that less fission poison is generated through a nuclear reaction by selecting an irradiating energy equal to 8 MeV or less than that. In the present invention, 7Li is changed to 7Be upon irradiation, but 7Be turns back to 7Li, again, after a half-life period, fifty-three (53) days; i.e., it can be used continuously. Although being a radioactive material, 7Be is enclosed within a lithium loop under the condition of being dissolved into the lithium, and it turns back to non-radioactive 7Li accompanying with an elapse of time. Further, determining the irradiating energy of the protons, to be equal to 2.0 MeV or less than that, brings about an area or region for generating neutrons, upon which no deceleration is necessary, and therefore, it is preferable to determine the irradiating energy to this, i.e., equal to 2.0 MeV or less than that, and also equal to 1.881 MeV threshold value energy or greater than that, at which the neutrons are generated. This 7Be generating in the nuclear reaction depending on the irradiating energy is one over several tens comparing to 2.5 MeV, as a source of generating neutrons, for use in the boron neutron capture therapy (BNCT), and it is the best to apply the protons of this energy band.
In this boron neutron capture therapy (BNCT) is applied a thermal neutron, equal to 0.5 eV or less than that, which is generated upon collision of the protons on a lithium target. In this instance, as an example of the reaction in the vicinity of the threshold value, at which no moderator is necessary to the neutron, determining the energy of the proton at 2 MeV, and current thereof to 20 mA, results into that a large thermal energy of 40 kW is given to the lithium. In spite of inputting this large heat therein, it is better for the lithium not to evaporate, and for the purpose of enabling a continuous operation thereof, there are the following necessities; i.e., that the lithium can always pass through a target portion of the neutron source, at high-speed and with stable thickness, so as to suppress the lithium from an increase of temperature thereof, and that the lithium as the target is always circulated through a lithium loop, which is built up to have an equipment for removing the heat from lithium on a way of the lithium loop, i.e., a closed loop of lithium. The lithium of the target portion of the neutron source is formed, being as thin as possible, for not disturbing loci of the neutrons generating into a direction of irradiation of the protons, and also for suppressing attenuation of the neutrons, and further for forming a stable lithium target stream made from a thin laminar flow, having such a thickness of 0.5 mm, approximately, being equal to 0.25 mm or greater than that in the depth thereof, into which the protons irradiated, being so-called a “bragg peak”, are absorbed, abruptly, and then onto this is hit a ray of protons, thereby generating the neutrons therefrom.
In such proton source as mentioned above, collision of the protons upon the flow of lithium target generates the neutrons to be applied for the purpose of the medical treatment. Also, at that time, the proton itself turns back to hydrogen by taking an electron of lithium in the periphery thereof into, and a part of this hydrogen is dissolved into the lithium, but much thereof reacts on the lithium to become lithium hydride. If assuming that the current of irradiating protons is 20 mA, an amount of hydrogen is only 6.53 g, if all of the protons turn back to the hydrogen and if irradiating thereon, continuously, for one year, and if assuming that there is 25 Kg of lithium, for example, and that an entire thereof come to be the lithium hydride, then an amount of the lithium hydride obtained is 52.24 g; i.e., this reaches only 0.21% of the amount of lithium, and in the condition of being dissolved into the lithium in the form of lithium hydride. On the other hand, the neutrons generating in the lithium upon irradiation of the protons are taken into 6Li, i.e. , the lithium isotope included in the lithium at 7.4%; therefore neutron capture 6Li are generating tritium, i.e., hydrogen isotope, a little bit thereof, through the nuclear reaction. An amount of tritium generating upon continuous irradiation of protons for one year is further small, only 2.44 μg, approximately. Nevertheless, the tritium is relatively long in the half-life period thereof, such as, 12.3 years; therefore, it is difficult to discharge this tritium as it is, but rather necessary to remove the tritium from, thereby not to be discharged into the atmosphere, but to be stored, or the tritium must be attenuated, if being discharged, in a concentration thereof, to be equal to or lower than a reference value determined according to a law related therewith. A part of this tritium also dissolves into the lithium, similarly, but almost thereof reacts on the lithium, thereby bringing about lithium tritiated.
In this manner, because the tritium is very little in the quantity thereof, and is further small quantity, judging from the amount of hydrogen reacting upon all of the lithium when there is 25 Kg of the lithium, it is in the condition of being dissolved in the lithium in the form of the lithium tritiated. Also, those, i.e., the lithium hydrated after reacting upon the lithium and also the lithium tritiated, are stable, in the high temperature thereof; i.e., not decomposed up to 686° C., and therefore is very small in the amount thereof, which is discharged as a gas in a vacuum discharge system or an argon cover gas system.
However, for the tritium generating, since there are cases of being discharged from the lithium, into the vacuum discharge system or the argon cover gas system, even with a very small possibility thereof, in such boron neutron capture therapy (BNCT) as mentioned above, it is necessary to remove this radioactive material, i.e., the tritium, from among the lithium loop, not to be discharged into the atmosphere. Also, almost all of the hydrogen and the hydrogen isotope, generating in a flow of lithium during the time of irradiation, come to be a lithium compound, being hardly decomposable; however, since a very little thereof, being dissolved under the condition of hydrogen atom, has a possibility of being gasified in such a place as being low in pressure thereof, etc., for example, that the gas, generating in a flow portion within vacuum, from the target portion up to a quench surface where the pressure is low among flows of the lithium and/or in a quench tank portion, forms bubbles and thereby rises up, or that it generates in a vacuum portion of an inlet portion of a pump. The gas generating causes to generate cavitations in the inlet portion of the pump, or change flows before and after a nozzle, or bring the flow of lithium to be unstable. Accordingly, also for circulating the flow of lithium in stable, there is a necessity of removing the gas of that hydrogen and hydrogen isotope.
Conventionally, as the technology for removing the tritium generating from a nuclear power facility, etc., there are already proposed several ones, as described in the following Patent Documents 1 to 4, for example. However, in the conventional arts, no proposal is made of a means for removing the tritium among from the lithium loop, for such neutron source as mentioned above. For this reason, in order to propagate such boron neutron capture therapy (BNCT) as mentioned above, widely, in medical facilities, it is desired to develop a lithium target system equipped with a tritium removal device, for enabling to form a stable lithium target flow, without diffusing the tritium into the atmosphere, and further to remove the tritium from among the lithium loop, with safety. Also, it is expected to be put in practical use as a target system for use in the neutron source of an accelerator driving type, other than the boron neutron capture therapy (BNCT).
In general, the tritium (T) cannot exist in the form of a tritium molecule where the hydrogen exists, but almost thereof exists under the condition of HT, combining with the hydrogen, and it is very hard to separate or divide those from each other, and the characteristics thereof are almost same to; therefore, the tritium must be processed together with the hydrogen when trying to remove the tritium from the hydrogen. Among hydrogen isotopes, general hydrogen is called, “light hydrogen”, distinguishing from deuterium and tritium; however herein, the light hydrogen is called only by “hydrogen”. Also, the gasses including the hydrogen and the tritium therein are called, “hydrogen isotope gasses”, and in this device, so as to emphasize or distinguish the tritium, remarkably, the radioactive material, but always including the light hydrogen therein, it is dare to call, not “hydrogen isotope gas”, but “tritium”, in case of the purpose of removal of the tritium.
[Patent Document 1] Japanese Patent Laying-Open No. 2005-127718 (2005);
[Patent Document 2] Japanese Patent Laying-Open No. Hei 06-331791 (1994);
[Patent Document 3] Japanese Patent Laying-Open No. Hei 05-341096 (1993); and
[Patent Document 4] Japanese Patent Laying-Open No. Hei 02-93399 (1990).
An object of the present invention, accomplished by taking the drawbacks in such tritium removal technologies of the conventional arts as mentioned above into the consideration thereof, is to provide a lithium target system, for enabling to obtain a stable lithium, with preventing the gas generated in the lithium from generating cavitations in an inlet of a pump, or from generating pulsation or fluid vibration in a valve or a nozzle, with applying a hydrogen and hydrogen isotope removal device for removing the tritium, with safety, without diffusing the hydrogen and the hydrogen isotope, i.e., the tritium, among from a lithium group for forming a lithium target flow.
The present invention, for accomplishing the object mentioned above, within a lithium loop for flowing lithium circularly, for allowing protons to reach up to a lithium target portion without colliding on a material, comprises a vacuum pump for maintain vacuum with differentially discharging the lithium target portion, and on discharge side of the vacuum pump, a hydrogen isotope removal filter and a hydrogen storage tank, and has a gas system, for accumulating the lithium, once, including hydrogen and tritium therein, generating in the lithium of the lithium target portion, being a neutron source, so as to keep a necessary NPSH (Net Positive Suction Head) for a pomp input portion due to a head of lithium liquid, and further for decelerating a flow within the tank, to let the hydrogen and the tritium gas in the lithium to float up and thereby collecting them in an upper portion of the tank, for removing gaseous components within the lithium so that no cavitations is generated due to gas, and for sucking the gas including the hydrogen and the tritium collected within the tank, thereby adjusting the gas pressure, wherein peripheries of equipment where the tritium gas gathers, including a portion of the pump for turning the lithium back to the neutron source, again, therein, are enclosed in an air-tightly hermetically sealed space of an inactive gas atmosphere, such as, argon, etc., and even in case where the tritium leaks out the lithium loop and an argon gas system thereof, by any change, into this hermetically sealed container, the tritium to be discharged together with a carrier gas from an inside of the hermetically sealed container is removed by a hydrogen isotope removal filter.
Thus, according to the present invention, there is provided a tritium removal device for a lithium loop, comprising: a neutron source 1 for colliding proton on a lithium flow, thereby generating neutrons; a lithium tank 11 for letting the lithium passing through this neutron source 1 to flow into through a flow passage 9, forming a quench surface of a lithium flow in the flow passage 9, and for temporality accumulating it therein, into which an exit of the flow passage forming the quench surface therein is connected, and thereby bringing the lithium tank 11 to be applicable with a gas pressure; and a lithium pump 17 for circulating and supplying the lithium of this lithium tank 11 to said neutron source 1 through a supply-side flow passage 9′, wherein hydrogen gas containing tritium therein, which is accumulated in a gas system of the lithium loop is removed by a hydrogen isotope removal filter, and further said lithium tank 11 and said lithium pump 17 are enclosed within a hermetically sealed container 7, and with this hermetically sealed container 7 is connected a discharge system flow passage through said hydrogen isotope removal filter.
This tritium removal device, being connected hermetically sealed container 7, enclosed all of gasses, into which the tritium leaks out by any change from the lithium tank 11 and the lithium pump 17 and the gas systems thereof, etc., within the hermetically sealed container 7 including the inactive gas therein, once, and the gas included in this hermetically sealed container 7 is discharged into the discharge system flow passage passing through the hydrogen isotope removal filter. For this reason, even in case where the gas leaks out from the lithium tank 11 and the lithium pump 17, etc., by any chance, it is possible to discharge that gas, after removing the tritium contained in the gas leaking out.
How much of the tritium is contained in that gas of the gas system, from which the tritium gas is removed, i.e., the partial pressure thereof is measured by a quadrupole mass spectrometer Q-mass, accurately, by attaching the quadrupole mass spectrometer Q-mass, being superior in air-tightness, to a connecting tube, after differentially discharging, the gas is diluted with air to be equal to or lower than a reference value depending on that partial pressure, and further is discharged while monitoring concentration of that diluted by a tritium monitor 38.
When the tritium gas is much, the gas is accumulated in a used-argon tank(s) 28, 29 and/or 37, once, and the partial pressure thereof is measured, accurately, again, by the quadrupole mass spectrometer Q-mass, and after being choked, a discharge gas is diluted with the air to be equal to or lower than the reference value depending on that partial pressure, and further the tritium gas in the diluted gas is discharged while monitoring concentration thereof by the tritium monitor 38.
The lithium tank 11 and the lithium pump 17 and the gas systems thereof, into which the tritium therein can be easily collected, are enclosed within the hermetically sealed container 7, and also, the gas leaking by any chance, as well as, the gas sucked from the gas system for adjustment of gas pressure are already the tritium therein through the hydrogen isotope removal filter; therefore, it never be diffused into the atmosphere, directly.
In the flow passage 9 on the discharge side, reaching from the neutron source 1 to the lithium tank 11 is provided a quench surface for defining a boundary between a gaseous phase on the neutron source 1 side and a liquid phase on the lithium tank 11 side, and a position of the same quench surface 8 is maintained by a very little pressure within the lithium tank 11. With doing this, it is possible, not only to prevent the lithium, flowing from the neutron source 1 into the lithium tank 11, from bringing bubbles into the lithium tank 11, as much as possible, but also to maintain the position of the quench surface 8 within the flow passage 9 to be high a little bit due to the very little pressure within the lithium tank 11, as well, and bringing NPSH at an inlet of the pump to be high by combining the head of the lithium liquid and the pressure within the lithium tank 11, thereby enabling the pump to operate with stability, without generating cavitations even under a reduced pressure.
The flow passages 9 and 9′ of the lithium are provided level gauges 10 and 24, at portions where they penetrate through a wall portion of the hermetically sealed container 7, so as to monitor existence of the lithium in those flow passages 9 and 9′ of the lithium. In particular, at a portion of the quench surface 8 mentioned above, which is provided in the flow passage 9 on discharge side, is provided the level gauge 10 for monitoring height of that quench surface 8; thereby achieving a stable management.
With the present invention explained in the above, the tritium removal device removes, in particular, when the tritium leaks from the lithium loop or an argon gas system of a cover gas by any chance, the tritium gas, i.e., the hydrogen and the hydrogen isotope, generating in the lithium flow upon irradiation of protons, and since the lithium target portion of the neutron source 1 is managed within vacuum, it is possible to suppress generation of the gas cavitations due to the gas even under the condition where NPSH is low in the inlet portion of the pump, and the quench surface is provided within a flow passage 9, further so as to retard a flow velocity of the lithium lower within the lithium tank 11, so that the gas can float up to the surface to be taken out from the argon gas in an upper portion of a lithium tank 11, in other words, it is possible to discharge that gas, after removing the tritium included in the gas when the tritium leaks out from the lithium tank 11 and the lithium pump 17, etc., i.e., places where the tritium gas is rich, by any chance, and therefore the tritium can be supplied, circularly, with safe and stability, i.e., preventing the tritium, included in the lithium discharged from the neutron source 1, from being leaked into an outside.
In accordance with the present invention, portion including a lithium tank 11, for storing lithium discharged from a neutron source, once therein, and also a pump, for returning the lithium from this lithium tank 11 back to the neutron source 1, again, are confined within an air-tight enclosed space of an inactive gas, such as, argon, etc., for example, wherein tritium accumulating in a gas system of a lithium loop is removed by a tritium removal filter, and further, even when the tritium leaks out, by any chance, from periphery of the lithium tank and/or the pump where hydrogen isotopes including the tritium can easily come together, by any chance, the tritium to be discharged from an inside of this hermetically sealed container is removed by the tritium removal filter, and thereby accomplishing the object mentioned above.
Hereinafter, detailed explanation will be made about the best mode for carrying out the present invention, by referring to an embodiment.
As is shown in
To a discharge side of this dry pump DRP are connected the turbo molecule pump TMP and the dry pump DRP, via a hydrogen isotope filter made of a hydrogen storage alloy, such as, Mg—Ni, etc., a valve, and a quadrupole mass spectrometer Q-mass. An orifice is provided between the valves in front of the quadrupole mass spectrometer Q-mass, so that they discharge differentially, thereby obtaining the pressure, under which the quadrupole mass spectrometer Q-mass can operate. By means of this quadrupole mass spectrometer Q-mass is made confirmation on a condition of removal of tritium after the hydrogen isotope filter, and the gas sucked by the turbo molecule pump 26 and the dry pump DRP through the lithium vapor trap 27, after being removed therefrom the hydrogen/hydrogen isotopes through a hydrogen isotope filter 30 made of the hydrogen storage alloy, such as, Mg—Ni, etc., is measured on hydrogen partial pressure by the quadrupole mass spectrometer Q-mass, and is discharged by the dry pump DRP into a used-argon tank 37 or 28, while other part of the gas is discharged through the orifice 33 and other remaining gases into the used-argon tank 37. When the used-argon tank 28 is filled up with, then the gas is discharged into another used-argon tank 29 by the dry pump DRP.
Also, in this gas flow passage system is provided a bypass passage, but this flow passage system is a route to be used when air comes into the system due to the maintenances of a lithium loop and/or a vacuum pump, etc, wherein suction is made by the turbomolecule pump 26 and the dry pump DRP from the proton passage tube 3 mentioned above through the lithium vapor trap 27. In this flow passage system, the dry pump DRP is connected through a hydrogen/oxygen storage alloy built-in filter 31, receiving a hydrogen/oxygen storage alloy, such as, Mg—Ni/Mg, etc., therein, in the place of such filter receiving the hydrogen storage alloy therein, as was mentioned above. When the air is mixed up with the gas, which is sacked by the turbo molecule pump 26 and the dry pump DRP from the proton passage tube 3 through the lithium vapor trap 27, this gas is sucked by the dry pump DRP through the hydrogen/oxygen storage alloy built-in filter 31. Further, after removing the hydrogen, the oxygen and nitrogen therefrom, passing through a hydrogen-cum-nitrogen trap 32, which receives a vanadium alloy, etc., therein, and is attached with a heater on an outside thereof, the remaining gas is discharged into the used-argon tank 37. This flow passage system has such structure that it operates to discharge the gas after passing through the nitrogen trap 32 through an orifice 34, and there is also prepared a bypass passage for sending the gas to the side of the quadrupole mass spectrometer Q-mass mentioned above. Both switching of those passages are conducted through a valve operation.
In the neutron generating chamber 5 is provided a rectifier plate 6 for forming a thin lithium target flow, and to this rectifier plate 6 is always supplied the lithium, continuously; therefore a lithium target flow of a thin laminar flow of lithium is formed on the surface thereof. By letting the protons accelerated by the accelerator 2 to collide upon the thin lithium target flow on the surface of this rectifier plate 6, neutrons are generated into a direction of collision. In the boron neutron capture therapy (BNCT), a cancer treatment is made by using the neutrons having such direction. Almost all of the protons take electrons in the periphery thereof in this neutron generating chamber 5; thereby becoming hydrogen, and further the tritium, i.e., the hydrogen isotope is generated from 6Li.
After the collision of protons on the lithium target flow on the rectifier plate 6 mentioned above, the lithium forming the lithium target flow is sent to the lithium tank 11 passing through a lithium flow passage 9 provided on a discharge side. An amount of the lithium in the lithium tank 11 is monitored by a level gauge 13, and within the same lithium tank is always stocked an approximately certain amount of the lithium.
To a bottom portion of the lithium tank 11 is connected a drain tank 12 through valves and a dipping-type electromagnetic pump 14. The lithium within this drain tank 12 is monitored by a level gauge 16. When the lithium in the drain tank 12 is in surplus, it is discharged into the drain tank 12 through an operation of the valve mentioned above, and also, when the lithium in the lithium tank 11 is in shortage for maintaining a desired liquid level, it is pumped up to the lithium tank 11 through driving of the dipping-type electromagnetic pump 14 mentioned above.
With the lithium tank 11 and the drain tank 12 mentioned above are connected an argon gas supply system and the dry pump DRP, through lithium vapor traps 27′ and 27″, each being made up by filling metal nets in a container and for removing the lithium vapor, wherein those lithium tank 11 and drain tank 12 are maintained under very little absolute pressure, such as, about 1 kPa, for example. This pressure of 1 kPa corresponds to pressure of a liquid head (i.e., height) of about 200 mm of lithium. This pressure is monitored by a pressure gauge P.
When driving, a gas system including the lithium tank 11 and the drain tank 12 is brought into a gas communicating condition, to be same in the pressure, and when an emergency occurs, the valve between the lithium tank 11 and the drain tank 12 is opened, so that the lithium within the lithium tank can be drained, emergently, through a free fall. The reason that the lithium tank 11 and the drain tank 12 to be vacuumed, other than the neutron generating chamber 5, are brought into the absolute pressure, such as, about 1 kPa, unwillingly, lies in that the lithium and/or the argon gas will not be discharged into the atmosphere, directly, even if it/they leak(s), since the pressure thereof is lower than that of the atmosphere, and further for the purpose of suppressing discharges of the hydrogen from the lithium and also the tritium gas under the pressure of argon gas within the lithium loop, down to the smallest, to enclose the tritium gas within the lithium, as much as possible therein, when executing the draining emergently, and thereby to increase the safety when executing the draining emergently. When executing the draining emergently, also the accelerator is stopped at a moment, automatically, and the gate valve 4 of the neutron generating chamber 5 in the lithium loop is also stopped at a moment, thereby to separate the lithium loop, having a very little possibility of producing the radioactive material therein; however, since the gate valve 4 is large and it takes time by a unit of 1 second to be completely closed, and since it is necessary to let the argon gas to permeate through the neutron generating chamber 5, firstly, after the lithium is lowered down a hot water surface thereof by a certain degree during the time when the emergency draining of lithium is executed, for the purpose of maintaining the vacuum of the accelerator and thereby accelerating re-starting of the accelerator, then the lithium flow passage 9 is connected to a lower side portion of the lithium tank 11, so that the argon gas of 1 kPa can be supplied to the neutron generating chamber 5 firstly when the lithium goes down to this connecting portion, and thereby allowing the gate valve 4 to take the time unit of 1 second for making the closure thereof. Although not shown in the figure, stabbing the lithium flow passage 9 into the lithium tank 11 from an upper flange surface thereof, i.e., so-called a dual-tube type, also brings about the similar effect to that; however, the dual tube makes a diameter of the lithium tank thick, and a liquid-level gauge must be inserted into a ring-like portion of the dual tube for the purpose of measuring the lithium surface in the lithium tank 11, but because the lithium has large surface tension, the liquid surface of the lithium is absorbed upwards in a narrow region, and this increases an error; therefore, the ring-like portion, into which the liquid-level gauge should be inserted, must be widen, considerably. This further brings the diameter of the lithium tank 11 to be thick, as well as, bringing about an increase of the amount or volume of the lithium, being a hazardous material; i.e., not being so preferable method; and therefore, herein, as is shown in
In the example shown in the figure, dry pumps DRP are connected on two stages, in series, and to each dry pump DRP on a back thereof are connected the first used-argon tank 28 and the second used-argon tank 29, wherein the hydrogen isotope gas discharged from the gas system, including the lithium tank 11 and the drain tank 12, is sent to a hydrogen isotope filter 42 by the dry pump DRP, and after being removed the hydrogen isotope gas therefrom, it is accumulated within the argon tank 28, and further if the used-argon gas tank 20 is filled up, then it is accumulated in the used-argon gas tank 29 through discharge by the dry pump DRP.
Also the gas accumulated in the used-argon tank 29, finally, is measured of the hydrogen partial pressure thereof, by the quadrupole mass spectrometer Q-mass, being differentially discharged from the used-argon tank 37 through the orifice 39, and the gas of the used-argon tank 37 is diluted with air by means of a blower, so that it comes to be equal to or less than a reference value depending on the tritium partial pressure thereof, and further it is discharged while being monitored the diluted concentration thereof by a tritium monitor 38.
Through adjustment of the argon gas pressure by the argon gas supply system and the dry pump DRP mentioned above, the liquid level of the lithium within the lithium tank 11 is maintained at a desired height. The lithium flow passage 9 reaching from the neutron generating chamber 5 to the lithium tank 11 is connected to the lithium tank 11 at the position in the middle thereof, being lower than the liquid level of the lithium in the lithium tank 11, so that a liquid surface is maintained, dividing a gaseous phase in an upper side and a liquid phase in a lower side on the way of the lithium flow passage, as well as, the quench surface 8. The fact that this quench surface 8 is positioned on a side of the lithium flow passage 9 other than the lithium tank 11 and also the height thereof bring about a function of preventing bubbles of the hydrogen gas including the tritium therein, from being brought into the lithium tank 11, by the lithium flowing from the neutron source 1 into the lithium tank 11.
To the lithium tank 11 is also connected the lithium pump 17, being built up with an induction electromagnetic pump. The lithium in the lithium tank 11 is circulated and supplied to a side of the rectifier plate 6 of the neutron generating chamber 5 mentioned above, passing through the lithium flow passage 9′ on the supply side, with driving by this lithium pump 17. In the lithium flow passage 9′ on the supply side is provided an electromagnetic flow meter 22, so that a flow amount of the lithium, passing through the lithium flow passage 9′ on the supply side, is measured.
Also, heat exchangers 18 and 23 are provided on the lithium pump 17 and the lithium flow passage 9′ on the supply side mentioned above, respectively, wherein the heat exchanger 18 cools or heats the lithium pump 17, while heat exchanger 23 cools or heats the lithium flow passage 9′ on the supply side, and thereby achieving an adjustment at the desired temperature. This lithium, which is adjusted on the temperature thereof, is supplied to the side of the rectifier plate 6 of the neutron generating chamber 5 mentioned above, through the valves. The heat exchangers 18 and 23 for the lithium pump 17 and the lithium flow passage 9′ on the supply side are cooled or heated, respectively, by cooler/heaters 20 and 21, each applying a heating medium therein, being heat-resistant against 350° C., thereby being maintained at the desired temperatures.
The lithium tank 11, the drain tank 12, the lithium pump 17 and the electromagnetic flow meter 22 mentioned above are enclosed within a hermetically sealed container 7, including the exchangers 18 and 23 for the lithium pump 17 and the lithium flow passage 9′ therein. To this hermetically sealed container 7 is connected the dry pump DRP, so that it is maintained to be negative pressure with respect to the atmosphere. Also, with this hermetically sealed container 7 is connected a argon supply tank 40 through the valves, and with the argon gas, being sent out from this argon supply tank to the hermetically sealed container 7, an inside of the hermetically sealed container 7 is maintained at an inactive gas atmosphere.
The gas discharged from the same hermetically sealed container 7 by the dry pump DRP, for decompressing the hermetically sealed container 7, is removed from the hydrogen, the oxygen and the nitrogen thereof, passing through the filter 35 made of the hydrogen/oxygen storage alloy, such as, Mg—Ni/Mg, etc., and also the nitrogen trap 36 made of the vanadium alloy, as the hydrogen isotope removal filter, and thereafter, the remaining gas is discharged into the used-argon tank 37. This system is attached for the purpose of processing the tritium, if it leaks out from the lithium and the argon gas system into the hermetically sealed container 7, by any chance. In case when discharging the gas from the used-argon tank 37, the hydrogen partial pressure is measured by the quadrupole mass spectrometer Q-mass, and the gas in the used-argon tank 37 is diluted with the air by the blower, depending on the tritium partial pressure thereof, so that it comes to be equal to or less than a reference value, and further the gas is discharged while monitoring the concentration thereof diluted.
The gas discharged into the inside of this used-argon tank 37 is measured of the tritium partial pressure, by the quadrupole mass spectrometer Q-mass, the gas therein being differentially discharged through the orifice 39, and if the tritium partial pressure is high, the gas is turned from the used-argon discharge tank 37, through a return pipe, back to the dry pump DRP, and also it circulates around the hydrogen isotope filter 35 and the nitrogen trap 36; thereby after being removed the tritium therefrom, it is turned back to the used-argon discharge tank 37. Thereafter, it is discharged, operationally, through the orifice 39, and as a result of measurement by the quadrupole mass spectrometer Q-mass, if the tritium partial pressure of the gas discharged into the used-argon discharge tank 37 is low, then the valve is opened to send the gas into a duct 41, wherein the gas is diluted with a large amount of air sent by the blower, into the duct 41, to be equal to or lower than a reference in the concentration thereof, and is discharged into the atmosphere. The tritium concentration of this discharge gas is monitored by the tritium monitor.
Within the tritium removal device for the lithium loop having such the structure as mentioned above, the hydrogen gas including the tritium therein, which is accumulated in the gas system for the lithium loop, is removed by the hydrogen isotope removal filter, and also the gas leaking out from the lithium tank 11 and the lithium pump 17, etc., where the hydrogen gas including the tritium therein can be easily accumulated, by any change, is held within the hermetically sealed container, once, and after being removed the tritium included in the gas within this hermetically sealed container, said gas is diluted and further discharged into the atmosphere while monitoring it by the tritium monitor 38. Therefore, a very little amount of the tritium contained in the lithium discharged from the neutron source 1 is removed by the hydrogen isotope removal filter, and further the partial pressure thereof is measured by the quadrupole mass spectrometer Q-mass, and thereafter it is diluted with the air by means of the blower, to be discharge while monitoring that the partial pressure thereof is equal to or lower than the reference, by the tritium monitor 38; i.e., it is possible to supply the lithium, circularly, while preventing the tritium from being leaked directly into an outside.
With the present invention, it can be applied as the tritium removal device for removing the tritium, a hydrogen isotope element generating in the lithium target to be the neutron source, from the lithium loop distributing the lithium, cyclically, in the in boron neutron capture therapy (BNCT), which will be applied for the purpose of a cancer medical treatment, for example.
1 . . . neutron source
7 . . . hermetically sealed container
8 . . . quench surface
9 . . . flow passage of lithium
9′. . . flow passage of lithium
11 . . . lithium tank
35 . . . filter
| Number | Date | Country | Kind |
|---|---|---|---|
| 2011-170599 | Aug 2011 | JP | national |
| Filing Document | Filing Date | Country | Kind | 371c Date |
|---|---|---|---|---|
| PCT/JP2012/063244 | 5/24/2012 | WO | 00 | 8/23/2013 |
