CN114152635B - Equivalent simulation device for neutron energy spectrum in human blood vessel after neutron external irradiation - Google Patents
Equivalent simulation device for neutron energy spectrum in human blood vessel after neutron external irradiation Download PDFInfo
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- 238000001228 spectrum Methods 0.000 title claims abstract description 62
- 238000004088 simulation Methods 0.000 title claims abstract description 59
- 210000004204 blood vessel Anatomy 0.000 title claims abstract description 38
- 210000004369 blood Anatomy 0.000 claims abstract description 86
- 239000008280 blood Substances 0.000 claims abstract description 86
- 239000000463 material Substances 0.000 claims description 41
- 238000002139 neutron reflectometry Methods 0.000 claims description 14
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 claims description 12
- -1 polyethylene Polymers 0.000 claims description 12
- 239000004698 Polyethylene Substances 0.000 claims description 11
- 229920000573 polyethylene Polymers 0.000 claims description 11
- ZCCIPPOKBCJFDN-UHFFFAOYSA-N calcium nitrate Chemical compound [Ca+2].[O-][N+]([O-])=O.[O-][N+]([O-])=O ZCCIPPOKBCJFDN-UHFFFAOYSA-N 0.000 claims description 10
- 239000011780 sodium chloride Substances 0.000 claims description 6
- 239000007832 Na2SO4 Substances 0.000 claims description 5
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 claims description 5
- PMZURENOXWZQFD-UHFFFAOYSA-L Sodium Sulfate Chemical compound [Na+].[Na+].[O-]S([O-])(=O)=O PMZURENOXWZQFD-UHFFFAOYSA-L 0.000 claims description 5
- 229910052925 anhydrite Inorganic materials 0.000 claims description 5
- YYRMJZQKEFZXMX-UHFFFAOYSA-L calcium bis(dihydrogenphosphate) Chemical compound [Ca+2].OP(O)([O-])=O.OP(O)([O-])=O YYRMJZQKEFZXMX-UHFFFAOYSA-L 0.000 claims description 5
- OSGAYBCDTDRGGQ-UHFFFAOYSA-L calcium sulfate Chemical compound [Ca+2].[O-]S([O-])(=O)=O OSGAYBCDTDRGGQ-UHFFFAOYSA-L 0.000 claims description 5
- 229910000150 monocalcium phosphate Inorganic materials 0.000 claims description 5
- 229910017604 nitric acid Inorganic materials 0.000 claims description 5
- 229910052939 potassium sulfate Inorganic materials 0.000 claims description 5
- OTYBMLCTZGSZBG-UHFFFAOYSA-L potassium sulfate Chemical compound [K+].[K+].[O-]S([O-])(=O)=O OTYBMLCTZGSZBG-UHFFFAOYSA-L 0.000 claims description 5
- 229910052938 sodium sulfate Inorganic materials 0.000 claims description 5
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 3
- 229910002804 graphite Inorganic materials 0.000 claims description 3
- 239000010439 graphite Substances 0.000 claims description 3
- 239000011259 mixed solution Substances 0.000 claims description 3
- 239000012188 paraffin wax Substances 0.000 claims description 3
- 229920003229 poly(methyl methacrylate) Polymers 0.000 claims description 3
- 239000004926 polymethyl methacrylate Substances 0.000 claims description 3
- 239000007787 solid Substances 0.000 claims description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 3
- 230000000694 effects Effects 0.000 abstract description 15
- 238000004364 calculation method Methods 0.000 abstract description 5
- 230000005855 radiation Effects 0.000 abstract description 5
- 239000000203 mixture Substances 0.000 description 13
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- 239000011734 sodium Substances 0.000 description 9
- 238000001514 detection method Methods 0.000 description 5
- 238000011156 evaluation Methods 0.000 description 4
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- 238000000342 Monte Carlo simulation Methods 0.000 description 3
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- 238000006243 chemical reaction Methods 0.000 description 2
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- LFQSCWFLJHTTHZ-UHFFFAOYSA-N Ethanol Chemical compound CCO LFQSCWFLJHTTHZ-UHFFFAOYSA-N 0.000 description 1
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- VVQNEPGJFQJSBK-UHFFFAOYSA-N Methyl methacrylate Chemical compound COC(=O)C(C)=C VVQNEPGJFQJSBK-UHFFFAOYSA-N 0.000 description 1
- 229920005372 Plexiglas® Polymers 0.000 description 1
- 239000004743 Polypropylene Substances 0.000 description 1
- 210000001367 artery Anatomy 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- HGLDOAKPQXAFKI-OUBTZVSYSA-N californium-252 Chemical compound [252Cf] HGLDOAKPQXAFKI-OUBTZVSYSA-N 0.000 description 1
- 239000003153 chemical reaction reagent Substances 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 230000001678 irradiating effect Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
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- 238000012545 processing Methods 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 210000003462 vein Anatomy 0.000 description 1
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
- G01N23/005—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by using neutrons
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
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Abstract
The invention relates to the technical field of nuclear radiation protection, and provides an equivalent simulation device for neutron energy spectrum in human blood vessels after neutron external irradiation, which is used for completing calculation of 24 Na specific activity in human blood because the neutron energy spectrum finally formed by scattering and slowing down an incident neutron in the equivalent simulation device is similar to the neutron energy spectrum in human model blood vessels after space neutron field irradiation after receiving neutron beam irradiation; the technical effects of reducing engineering difficulty and cost and improving the irradiation efficiency of blood are achieved.
Description
Technical Field
The invention relates to the technical field of nuclear radiation protection, in particular to an equivalent simulation device of neutron energy spectrum in a human blood vessel after neutron external irradiation.
Background
In nuclear explosion and nuclear accidents, neutron external irradiation is an important source of human radiation. Therefore, when personnel receive nuclear radiation, the neutron external irradiation dose is timely and accurately estimated, and the method has important value for the medical treatment of wounded and the estimation of accident hazard degree.
The dose evaluation method for measuring the induced radioactivity generated after the human body is irradiated by neutrons is called a neutron activation method, and is an external irradiation dose evaluation method with neutron specificity. Specifically, when a person is irradiated by neutron rays, neutrons can react with 23 Na elements in the human body in a radiation trapping way to generate radionuclide 24 Na, and the neutron external irradiation dose can be estimated by measuring the specific activity of 24 Na in a blood sample of the irradiated person. The neutron activation method has the advantages of convenient sample acquisition, short measurement time and capability of carrying out rapid dose evaluation at the accident site.
However, in the process of performing external irradiation dose evaluation, a neutron external irradiation experiment cannot be directly performed by using a human body, but instead irradiation is performed by using a human body model with the same standard as the real human body structure, density and element composition; however, current human models for irradiation experiments, such as simplified human digital models BOMB, MIRD provided by the international radiological protection committee (ICRP), do not give the distribution of human blood vessels and blood; other complex digital models such as VIP-Man, germany GFS, china CNMAN, etc. also only characterize major arteries and veins of the human body, and do not consider the detailed distribution of the vessels. Therefore, the method is not suitable for a scene of calculating the conversion coefficient from 24 Na specific activity to neutron external irradiation dose in human blood by a neutron activation method.
If the conversion coefficient from 24 Na specific activity in human blood to neutron external irradiation dose is calculated by adopting a human body physical model, the method has the following disadvantages:
1) Because the distribution of human blood vessels, particularly capillaries, is complex, if the human body physical model containing accurate human blood vessels and blood distribution is manufactured, the problems of great difficulty and high manufacturing cost are faced; 2) Because the neutron beam of a large neutron irradiation device such as a reactor and a spallation neutron source is generally linear, the device is not suitable for irradiating the whole body of a human body physical model; in order to uniformly irradiate the human body physical model, a neutron field with higher fluence and good uniformity needs to be provided in a sufficient three-dimensional space, the difficulty of maintaining the uniformity of the neutron field in a large space is high, and an experimental platform capable of providing the high-quality space neutron field is few; 3) The blood is distributed throughout the whole body but the mass of the blood is only 7-8% of the human body, when the space neutron field irradiates the human body physical model, the neutron injection quantity which can reach the blood is very small due to the effects of scattering, slowing down, absorbing and the like of neutrons and human body tissue organs, namely the irradiation efficiency of the blood in the phantom is low.
Therefore, an equivalent simulation device for measuring neutron energy spectrum in human blood vessels after neutron external irradiation with high efficiency is needed.
Disclosure of Invention
The invention provides an equivalent simulation device for neutron energy spectrum in human blood vessels after neutron external irradiation, which is used for calculating 24 Na specific activity in human blood and has the technical effects of simple structure, easy processing and good simulation effect.
In order to achieve the above purpose, the invention provides an equivalent simulation device for neutron energy spectrum in human blood vessel after neutron external irradiation, wherein the equivalent simulation device is a box-shaped container structure for receiving neutron external irradiation, and the relative error between the neutron energy spectrum in the equivalent simulation device after neutron external irradiation and the normalized intensity of the corresponding energy point of the neutron energy spectrum in human body digital model after neutron external irradiation is less than 5%;
The box-shaped container structure comprises a tissue simulation part and a neutron reflection part which are sequentially arranged from the near to the far along the neutron beam direction; the tissue simulation part comprises an equivalent tissue material chamber which is formed by surrounding a front side wall, a rear side wall, a left side wall, a right side wall, an upper side wall, a lower side wall and the side walls; the equivalent tissue material chamber is a closed chamber for filling equivalent tissue material simulating human tissue; wherein,
The side wall which firstly receives neutron beam irradiation is a front side wall, and a blood sample part is arranged on the rear side wall; forming a blood sample chamber filled with a blood sample simulating human blood in the blood sample part;
the neutron reflecting portion is used for reflecting neutrons which pass through the equivalent tissue portion and the blood sample portion to the neutron reflecting portion to the blood sample portion.
Further, it is preferable that the neutron reflecting portion is a polyethylene solid body or a closed chamber filled with a neutron reflecting material other than polyethylene.
Further, it is preferable that the neutron reflecting material other than polyethylene is one of water, paraffin wax or graphite.
Further, preferably, the tissue simulation part is a cuboid with a length of 17.1cm, a width of 38cm and a height of 23cm, and the long side of the tissue simulation part is parallel to the direction of neutron beam; the thickness of the front side wall is 2.2cm, and the thickness of the side walls except the front side wall is 3cm;
The neutron reflection part is a cuboid with the length of 12.9cm, the width of 38cm and the height of 23 cm; the long side of the neutron reflection part is parallel to the direction of neutron beam;
The blood sample part is a cuboid with the length of 5.2cm, the width of 5.2cm and the thickness of 4mm, and the distance between the bottom of the blood sample part and the bottom surface of the equivalent tissue material chamber is 6.2cm; the thick sides of the blood sample part are parallel to the long sides of the tissue simulation part, and the wall thickness of the blood sample part is 1mm.
Further, it is preferable that the tissue simulation part and the neutron reflection part are polyethylene members having a density of 0.96g/cm 3; the blood sample portion was a polymethyl methacrylate member having a density of 1.15g/cm 3.
Further, preferably, the mass ratio of the mixed solution ;H2O、C2H6O、NH4NO3、Ca(NO3)2、Ca(H2PO4)2、K2SO4、HNO3、Na2SO4、CaSO4、NaCl of H2O、C2H6O、NH4NO3、Ca(NO3)2、Ca(H2PO4)2、K2SO4、HNO3、Na2SO4、CaSO4、NaCl and MgCl to MgCl of the equivalent tissue material is: 49.076%:34.432%:5.626%:5.231%:3.721%:0.768%:0.411%:0.304%:0.185%:0.125%:0.121%.
Further, it is preferable that the incidence position of the neutron beam is 7cm higher than the bottom surface of the tissue simulation part, and when the beam spot radius of the neutron beam is 1cm, the bottom of the blood sample part is located 2.2cm above the beam spot center of the neutron beam.
According to the invention, by establishing the equivalent simulation device of the neutron energy spectrum in the human blood vessel after neutron external irradiation with a simple structure, after receiving neutron beam irradiation, the neutron energy spectrum finally formed by scattering and slowing the incident neutrons in the equivalent simulation device is similar to the neutron energy spectrum shape in the human model blood vessel after space neutron field irradiation, so that the neutron energy spectrum simulation device can be used for completing calculation of 24 Na specific activity in human blood, and has the beneficial effects that:
1) The human body physical model containing accurate human body blood vessels and blood distribution is not required to be manufactured, so that the detection engineering quantity and the detection cost are greatly reduced;
2) By using the equivalent simulation device, on the premise that the neutron energy spectrum of the blood sample after neutron external irradiation is the same as the neutron energy spectrum in the blood vessel of the human body after neutron external irradiation, the neutron fluence of the blood sample is far higher than the neutron fluence in the blood vessel when the human body model is irradiated, thereby achieving the technical effect of greatly improving the irradiation efficiency;
3) Unlike the human physical model, which needs a uniform space neutron field, the irradiation requirement can be met by adopting linear neutron beam current, so that the experimental conditions are easier to meet.
Drawings
FIG. 1 is a schematic structural diagram of an equivalent simulation device of neutron energy spectrum in a human blood vessel after neutron external irradiation according to an embodiment of the present invention;
FIG. 2 is a spectrum of an incident neutron beam according to an embodiment of the present invention;
FIG. 3 is a diagram showing a comparison between neutron spectrum in a human body physical model vessel and neutron spectrum in an equivalent simulation device according to an embodiment of the present invention;
1, a tissue simulation part; 2. equivalent tissue material; 3. a blood sample section; 4. a blood sample; 5. a neutron reflection unit;
the achievement of the objects, functional features and advantages of the present invention will be further described with reference to the accompanying drawings, in conjunction with the embodiments.
Detailed Description
It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the scope of the invention.
Referring to fig. 1, fig. 1 is a schematic structural diagram of an equivalent simulation device for neutron energy spectrum in a human blood vessel after neutron external irradiation according to an embodiment of the present invention.
Example 1
The equivalent simulation device is a box-shaped container structure which receives neutron external irradiation, and the box-shaped container structure comprises a tissue simulation part 1 and a neutron reflection part 5 which are sequentially arranged from the near to the far along the neutron beam direction; the tissue simulation part 1 comprises an equivalent tissue material chamber which is formed by surrounding a front side wall, a rear side wall, a left side wall, a right side wall, an upper side wall, a lower side wall and the side walls; the equivalent tissue material chamber is a closed chamber for filling the equivalent tissue material 2 simulating human tissue; when the beam spot radius of the neutron beam is 1cm, the side wall which is firstly irradiated by the neutron beam is the front side wall, and the rear side wall is provided with a blood sample part 3; the bottom of the blood sample part 3 is positioned at a position 2.2cm above the center of a beam spot of the neutron beam, so that the phenomenon that the blood sample part is directly irradiated by the neutron beam to cause excessive high-energy neutrons reaching the blood sample part 3 is avoided; forming a blood sample chamber filled with a blood sample 4 simulating human blood in the blood sample part 3; the neutron reflecting section 5 is for reflecting neutrons reaching the neutron reflecting section 5 through the equivalent tissue section and the blood sample section to the blood sample section 3. The device has the technical effect of avoiding the excessive high-energy neutrons reaching the blood sample part caused by the direct irradiation of the sample by neutron beam. Because the farther the neutron beam is from the sample, the more serious the neutron moderating scattering is, the less the high-energy neutron is, and when the bottom of the blood sample part 3 is positioned at the position 2.2cm above the beam spot center of the neutron beam, the optimal position is simulated, and the neutron energy spectrum in the position is closest to the energy spectrum in a real blood vessel.
That is, the equivalent simulation device is mainly composed of a box-like container structure and an equivalent tissue material 2 and neutron reflecting material within the container. Wherein the neutron reflecting material is located behind the equivalent tissue material 2 along the direction of the neutron beam incidence. The neutron reflecting part 5 is a polyethylene solid body, the length is 12.9cm, the width is 38cm, the height is 23cm, and the material is density 0.96g/cm 3; as shown in fig. 1, the longitudinal direction of the neutron reflection unit 5 is the direction along which the X axis is located; the equivalent tissue material 2 is contained in an equivalent tissue material cavity of the tissue simulation part 1, and the external dimension of the tissue simulation part 1 is 17.1cm long, 38cm wide and 23cm high; the material is polyethylene with the density of 0.96g/cm 3; the nearest side wall to the neutron beam is a front side wall, the thickness of the front side wall is 2.2cm, and the thickness of the other five surfaces is 3cm; as shown in fig. 1, the longitudinal direction of the tissue simulation unit 1 is the direction along which the X-axis is located. The equivalent tissue material 2 is positioned in the equivalent tissue material cavity, the geometric dimension of the equivalent tissue material 2 is 11.9cm long, 32cm wide and 17cm high, the equivalent tissue material 2 is an alcohol mixed solution of a plurality of inorganic salts and is weak acid, ca (H 2PO4)2 has higher solubility in a weak acid environment and can not precipitate, the material of the equivalent tissue material 2 simulates the main element composition of a human body, the density is 1.05g/cm 3, the element composition is shown in Table 1, and the chemical composition is shown in Table 2.
TABLE 1 elemental composition of equivalent tissue material 2
TABLE 2 chemical composition of equivalent tissue material 2
| Composition of the components | H2O | C2H6O | NH4NO3 | Ca(NO3)2 | Ca(H2PO4)2 | K2SO4 | HNO3 | Na2SO4 | CaSO4 | NaCl | MgCl |
| Mass ratio% | 49.076 | 34.432 | 5.626 | 5.231 | 3.721 | 0.768 | 0.411 | 0.304 | 0.185 | 0.125 | 0.121 |
The blood sample 4 is arranged in a blood sample chamber of the blood sample part 3, the blood sample part is a cuboid with the length of 5.2cm, the width of 5.2cm and the thickness of 4mm, and the distance between the bottom of the blood sample part and the bottom surface of the equivalent tissue material chamber is 6.2cm; the wall thickness of the blood sample portion was 1mm, i.e., the blood sample portion could accommodate a blood sample having a volume of 5cm×5cm×2 mm. As shown in fig. 1, the thickness direction of the blood sample part 3 is parallel to the X-axis direction. The geometric dimensions of the blood sample 4 are 5cm long, 5cm wide, 2mm thick, and density of 1.06g/cm 3, and the elemental compositions are shown in Table 3; the blood sample portion 3 was a 1mm thick plexiglass (polymethyl methacrylate) container having a density of 1.15g/cm 3. The blood sample part 3 is tightly attached to the rear side wall of the equivalent tissue material chamber, and the distance between the bottom surface of the blood sample part 3 and the outer bottom surface of the equivalent simulation device is 9.2cm.
The composition of the blood sample 4 is specifically set according to the detection result of the blood composition in the actual scene. The blood sample may be a real human blood, may be replaced with a sodium chloride solution having the same sodium content as blood, or may be formed by using other chemical reagents having the same composition as the blood elements, and is not particularly limited herein. In this example, human blood was used as the blood sample, and the elemental composition thereof is shown in Table 3.
TABLE 3 elemental composition of blood sample 4
The neutron beam is incident at a position 7cm away from the bottom of the equivalent simulation device, and the beam spot radius of the beam is 1cm. The energy spectrum of the incident neutron beam is shown in fig. 2, and is the watt fission spectrum of the neutron source californium-252, the horizontal axis is neutron energy, and the vertical axis is normalized intensity, namely when the total emission probability is 1, the emission probability of neutrons with different energies is shown.
Neutrons reach the blood sample 4 after being slowed down and scattered by the side wall of the tissue simulation part 1 and the equivalent tissue material 2; after passing through the side wall of the tissue simulation part 1 and the equivalent tissue material 2, part of neutrons are reflected by the neutron reflection part to reach the blood sample 4, and the neutron energy spectrum I in the blood sample 4 is obtained through Monte Carlo simulation calculation, and the neutron energy spectrum I is the neutron energy spectrum in the equivalent simulation device.
The obtained neutron spectrum is compared with a reference neutron spectrum obtained in advance, and the comparison result is shown in figure 3.
The method for acquiring the reference neutron energy spectrum comprises the following steps: the method comprises the steps of uniformly radiating a human body digital model containing main blood vessels of a human body outside a neutron field; and calculating neutron energy spectrum in the blood vessel of the phantom when the front surface of the cf-252 neutron source uniformly irradiates the human body digital model through Monte Carlo simulation, namely, obtaining the reference neutron energy spectrum. The human body digital model containing the main blood vessel of the human body is constructed according to the human body tissue and organ data given by the ICRP110 publication. The reference energy spectrum is neutron energy spectrum in the human body model blood vessel.
FIG. 3 shows a graph of the neutron spectrum in a vessel of a physical model of a human body versus the neutron spectrum in an equivalent simulation device; by observing fig. 3, it is found that the neutron spectrum in the equivalent simulation device is similar to the neutron spectrum in the blood vessel of the human body model in shape, but the intensity of the neutron spectrum in the equivalent simulation device is 109 times of that in the blood vessel of the human body model, and the fluctuation (relative error) of the ratio obtained by dividing the normalized intensities of the two energy spectrums corresponding to the energy points is less than 5%.
Example 2
The neutron reflection part 5 is a closed cavity filled with neutron reflection material, and the neutron reflection material is one of water, paraffin or graphite except polyethylene; the material of the container main body of the equivalent simulation device is polypropylene with the density of 0.96g/cm 3. Other experimental conditions are the same as those of the embodiment 1, an equivalent simulation device of the neutron energy spectrum in the blood vessel of the human body after neutron external irradiation is established, and a neutron energy spectrum II in the blood sample 4 is obtained through Monte Carlo simulation calculation.
Comparing the neutron spectrum II with the reference spectrum, the shape of the neutron spectrum II is similar, the intensity of the neutron spectrum in the equivalent simulation device is 109 times of that of the neutron spectrum in the blood vessel of the human body model, and the fluctuation (relative error) of the ratio obtained by dividing the normalized intensities of the two energy spectrums corresponding to the energy points is less than 5%.
The equivalent simulation device of the neutron energy spectrum in the human body blood vessel after the neutron external irradiation is irradiated, after receiving the neutron beam irradiation, the neutron energy spectrum formed by the incident neutrons after being scattered and slowed down in the equivalent simulation device is similar to the neutron energy spectrum shape in the human body model blood vessel after the space neutron field irradiation, so that the equivalent simulation device can be used for completing the calculation of 24 Na specific activity in the human body blood; the method has the characteristics that a human body physical model containing accurate human body blood vessels and blood distribution is not required to be manufactured, so that the detection engineering quantity and the detection cost are greatly reduced; by using the equivalent simulation device, on the premise that the neutron energy spectrum of the blood sample after neutron external irradiation is the same as the neutron energy spectrum in the blood vessel of the human body after neutron external irradiation, the neutron fluence of the blood sample is far higher than the neutron fluence in the blood vessel when the human body model is irradiated, thereby achieving the technical effect of greatly improving the irradiation efficiency; unlike the human physical model which needs uniform space neutron field, the irradiation requirement can be met by adopting linear neutron beam flow, and the method has the technical effect that experimental conditions are easier to meet.
Finally, it should be noted that the above-mentioned embodiments are merely for illustrating the technical solution of the present invention and not for limiting the same, and although the present invention has been described in detail with reference to the preferred embodiments, it should be understood by those skilled in the art that modifications and equivalents may be made to the technical solution of the present invention without departing from the spirit and scope of the technical solution of the present invention.
Claims (5)
1. An equivalent simulation device of neutron energy spectrum in human blood vessel after neutron external irradiation is characterized in that,
The equivalent simulation device is a box-shaped container structure which receives neutron external irradiation, and the relative error of the normalized intensity of the neutron energy spectrum in the equivalent simulation device after neutron external irradiation and the corresponding energy point of the neutron energy spectrum in the blood vessel of the human body digital model after neutron external irradiation is less than 5%;
The box-shaped container structure comprises a tissue simulation part and a neutron reflection part which are sequentially arranged from the near to the far along the neutron beam direction; the tissue simulation part comprises a front side wall, a rear side wall, a left side wall, a right side wall, an upper side wall, a lower side wall and an equivalent tissue material chamber surrounded by the side walls; the equivalent tissue material chamber is a closed chamber for filling equivalent tissue material simulating human tissue; the equivalent tissue material is a mixed solution of H2O、C2H6O、NH4NO3、Ca(NO3)2、Ca(H2PO4)2、K2SO4、HNO3、Na2SO4、CaSO4、NaCl and MgCl;
The mass ratio of H2O、C2H6O、NH4NO3、Ca(NO3)2、Ca(H2PO4)2、K2SO4、HNO3、Na2SO4、CaSO4、NaCl to MgCl is as follows: 49.076%:34.432%:5.626%:5.231%:3.721%:0.768%:0.411%:0.304%:0.185%:0.125%:0.121%;
wherein,
The side wall which firstly receives neutron beam irradiation is a front side wall, and a blood sample part is arranged on the rear side wall; forming a blood sample chamber filled with a blood sample simulating human blood within the blood sample portion; the incidence position of the neutron beam is 7cm higher than the bottom surface of the tissue simulation part; when the beam spot radius of the neutron beam is 1cm, the bottom of the blood sample part is positioned at a position 2.2cm above the beam spot center of the neutron beam;
the neutron reflecting portion is configured to reflect neutrons, which have passed through the tissue simulating portion and the blood sample portion to the neutron reflecting portion, to the blood sample portion.
2. The device for equivalently simulating the neutron energy spectrum in a human blood vessel after neutron irradiation according to claim 1, wherein the device comprises a plurality of sensors,
The neutron reflecting part is a polyethylene solid body or a closed cavity filled with neutron reflecting materials except polyethylene.
3. The device for equivalently simulating neutron energy spectrum in human blood vessels after neutron irradiation according to claim 2, wherein the device comprises a plurality of sensors,
The neutron reflecting material except polyethylene is one of water, paraffin or graphite.
4. The device for equivalently simulating the neutron energy spectrum in a human blood vessel after neutron irradiation according to claim 1, wherein the device comprises a plurality of sensors,
The tissue simulation part is a cuboid with the length of 17.1cm, the width of 38cm and the height of 23cm, and the long side of the tissue simulation part is parallel to the direction of neutron beam; the thickness of the front side wall is 2.2cm, and the thickness of the side walls except the front side wall is 3cm;
the neutron reflecting part is a cuboid with the length of 12.9cm, the width of 38cm and the height of 23 cm; the long side of the neutron reflection part is parallel to the direction of the neutron beam;
The blood sample part is a cuboid with the length of 5.2cm, the width of 5.2cm and the thickness of 4mm, and the distance between the bottom of the blood sample part and the bottom surface of the equivalent tissue material chamber is 6.2cm; the thick side of the blood sample part is parallel to the long side of the tissue simulation part, and the wall thickness of the blood sample part is 1mm.
5. The equivalent simulation device of the neutron energy spectrum in the blood vessel of the human body after the neutron external irradiation according to claim 4, wherein the tissue simulation part and the neutron reflection part are polyethylene pieces with the density of 0.96g/cm 3; the blood sample portion was a polymethyl methacrylate member having a density of 1.15g/cm 3.
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Citations (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP1112105A1 (en) * | 1998-09-10 | 2001-07-04 | Radicon AB | Neutron radiation installation for treatment of cancer |
| WO2005119295A1 (en) * | 2004-06-04 | 2005-12-15 | Bc Cancer Agency | Method and apparatus for verifying radiation dose distributions |
| CN101360522A (en) * | 2005-12-19 | 2009-02-04 | Lumen联合公司 | Apparatus for irradiation of fluid with electromagnetic radiation and method for the same |
| CN102176047A (en) * | 2011-03-04 | 2011-09-07 | 中国原子能科学研究院 | Neutron personal dosimeter with energy compensation |
| EP2421006A1 (en) * | 2010-08-20 | 2012-02-22 | Ludwig-Maximilians-Universität München | Method for producing isotopes, in particular method for producing radioisotopes by means of gamma-beam irradiation |
| CN102568287A (en) * | 2010-12-24 | 2012-07-11 | 中国科学院深圳先进技术研究院 | Multimodality bionic body model |
| EP2888998A2 (en) * | 2013-12-27 | 2015-07-01 | Seiko Epson Corporation | Blood component analyzing method and blood component analyzing apparatus |
| JP2016214760A (en) * | 2015-05-25 | 2016-12-22 | 株式会社東芝 | Treatment device for boron neutron capture therapy, and control method thereof |
| CN107195345A (en) * | 2017-06-09 | 2017-09-22 | 中国科学院合肥物质科学研究院 | The accurate simulation system of neutron irradiation damage and its algorithm all can be composed |
| JP2018161449A (en) * | 2017-03-27 | 2018-10-18 | 株式会社八神製作所 | Neutron deceleration radiation equipment and extension collimator |
| EP3556431A1 (en) * | 2017-01-11 | 2019-10-23 | Neuboron Medtech Ltd. | Medical image-based method for deconstructing tissue element mass ratio and method for establishing geometric model |
| WO2020211583A1 (en) * | 2019-04-17 | 2020-10-22 | 中硼(厦门)医疗器械有限公司 | Neutron capture therapy system |
| WO2020242331A2 (en) * | 2019-05-31 | 2020-12-03 | Qatar Foundation For Education, Science And Community Development | Coincidence detection system for measuring arterial blood time-activity curves and methods of using same |
| CN112529950A (en) * | 2020-12-08 | 2021-03-19 | 中国人民解放军军事科学院军事医学研究院 | Organism voxel model implementation method for radiation dose evaluation |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4603823B2 (en) * | 2003-10-14 | 2010-12-22 | キヤノン株式会社 | Radiation imaging apparatus, radiation imaging method and program |
| US8509879B2 (en) * | 2007-11-06 | 2013-08-13 | The Regents Of The University Of California | Apparatus and method for widefield functional imaging (WiFI) using integrated structured illumination and laser speckle imaging |
| US20160174923A1 (en) * | 2014-12-19 | 2016-06-23 | Purdue Research Foundation | Neutron generator for measuring trace elements in tissue |
-
2021
- 2021-10-15 CN CN202111203042.1A patent/CN114152635B/en active Active
Patent Citations (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP1112105A1 (en) * | 1998-09-10 | 2001-07-04 | Radicon AB | Neutron radiation installation for treatment of cancer |
| WO2005119295A1 (en) * | 2004-06-04 | 2005-12-15 | Bc Cancer Agency | Method and apparatus for verifying radiation dose distributions |
| CN101360522A (en) * | 2005-12-19 | 2009-02-04 | Lumen联合公司 | Apparatus for irradiation of fluid with electromagnetic radiation and method for the same |
| EP2421006A1 (en) * | 2010-08-20 | 2012-02-22 | Ludwig-Maximilians-Universität München | Method for producing isotopes, in particular method for producing radioisotopes by means of gamma-beam irradiation |
| CN102568287A (en) * | 2010-12-24 | 2012-07-11 | 中国科学院深圳先进技术研究院 | Multimodality bionic body model |
| CN102176047A (en) * | 2011-03-04 | 2011-09-07 | 中国原子能科学研究院 | Neutron personal dosimeter with energy compensation |
| EP2888998A2 (en) * | 2013-12-27 | 2015-07-01 | Seiko Epson Corporation | Blood component analyzing method and blood component analyzing apparatus |
| JP2016214760A (en) * | 2015-05-25 | 2016-12-22 | 株式会社東芝 | Treatment device for boron neutron capture therapy, and control method thereof |
| EP3556431A1 (en) * | 2017-01-11 | 2019-10-23 | Neuboron Medtech Ltd. | Medical image-based method for deconstructing tissue element mass ratio and method for establishing geometric model |
| JP2018161449A (en) * | 2017-03-27 | 2018-10-18 | 株式会社八神製作所 | Neutron deceleration radiation equipment and extension collimator |
| CN107195345A (en) * | 2017-06-09 | 2017-09-22 | 中国科学院合肥物质科学研究院 | The accurate simulation system of neutron irradiation damage and its algorithm all can be composed |
| WO2020211583A1 (en) * | 2019-04-17 | 2020-10-22 | 中硼(厦门)医疗器械有限公司 | Neutron capture therapy system |
| WO2020242331A2 (en) * | 2019-05-31 | 2020-12-03 | Qatar Foundation For Education, Science And Community Development | Coincidence detection system for measuring arterial blood time-activity curves and methods of using same |
| CN112529950A (en) * | 2020-12-08 | 2021-03-19 | 中国人民解放军军事科学院军事医学研究院 | Organism voxel model implementation method for radiation dose evaluation |
Non-Patent Citations (8)
| Title |
|---|
| 252Cf裂变中子源在组织等效模体中的中子和γ辐射剂量分布的计算;纪刚，等;《中华放射医学与防护杂志》;20010825;第21卷(第04期);第244-246页 * |
| Neutron activated Samarium-153 microparticles for transarterial radiaembolization of liver tumour with post-procedure imaging capabilities;Hashikin N, et al;《Plos one》;20150918;第10卷(第09期);第0138106 * |
| Neutron and photo dose rates in a D-T neutron generator facility:MCNP simulations and experiments;Xu x, et al;《Health physics》;20200124;第118卷(第06期);第600-608页 * |
| 中子照射后人体剂量测量方法的改进;成杰, 等;《中国辐射卫生》;20110620;第20卷(第02期);第234-240页 * |
| 人体血液模拟液NaCl中中子感生~(24)Na的活度:源-样品距和照射时间的影响;张金钊, 等;《核技术》;20120930;第35卷(第09期);第661-664页 * |
| 测量血钠活度估算中子照射人体剂量方法与进展;谢向东，等;《中国辐射卫生》;20110330;第20卷(第01期);第124-127页 * |
| 激光辐照活体皮肤层状组织的光热作用数值模拟研究;陈燕，等;《应用激光》;20071015;第27卷(第05期);第382-386页 * |
| 用人体模型和组织等效剂量计测量临界事故情况下人体内的中子和r射线吸收剂量;Hiroki S, 等;《中国核学会》;20141231(第01期);第56-59页 * |
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