CN112881238A - Method and experimental system for determining tritium diffusion coefficient based on release rate - Google Patents
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- 229910052722 tritium Inorganic materials 0.000 title claims abstract description 126
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 title claims abstract description 123
- 238000009792 diffusion process Methods 0.000 title claims abstract description 74
- 238000000034 method Methods 0.000 title claims abstract description 28
- 239000000463 material Substances 0.000 claims abstract description 43
- 238000010438 heat treatment Methods 0.000 claims abstract description 32
- 238000012806 monitoring device Methods 0.000 claims abstract description 25
- 230000000694 effects Effects 0.000 claims abstract description 8
- 239000007789 gas Substances 0.000 claims description 33
- 238000001816 cooling Methods 0.000 claims description 13
- 238000005259 measurement Methods 0.000 claims description 12
- 238000002474 experimental method Methods 0.000 claims description 9
- 238000011084 recovery Methods 0.000 claims description 7
- 239000012159 carrier gas Substances 0.000 claims description 6
- 238000012544 monitoring process Methods 0.000 claims description 6
- 239000002912 waste gas Substances 0.000 claims description 6
- 230000008569 process Effects 0.000 claims description 5
- 230000008859 change Effects 0.000 claims description 4
- 230000005284 excitation Effects 0.000 claims description 4
- 238000012937 correction Methods 0.000 claims description 3
- 238000001514 detection method Methods 0.000 abstract description 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 26
- 229910002804 graphite Inorganic materials 0.000 description 24
- 239000010439 graphite Substances 0.000 description 24
- 239000001307 helium Substances 0.000 description 8
- 229910052734 helium Inorganic materials 0.000 description 8
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 8
- 239000000446 fuel Substances 0.000 description 5
- 239000011159 matrix material Substances 0.000 description 5
- 239000007770 graphite material Substances 0.000 description 4
- 239000002296 pyrolytic carbon Substances 0.000 description 4
- 241000013033 Triso Species 0.000 description 3
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- 229910052799 carbon Inorganic materials 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 239000002245 particle Substances 0.000 description 2
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 description 2
- 229910010271 silicon carbide Inorganic materials 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000000919 ceramic Substances 0.000 description 1
- 238000009694 cold isostatic pressing Methods 0.000 description 1
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- 238000010586 diagram Methods 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
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- 239000012535 impurity Substances 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000001678 irradiating effect Effects 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 239000012466 permeate Substances 0.000 description 1
- 239000000047 product Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000003904 radioactive pollution Methods 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
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- G01N15/00—Investigating characteristics of particles; Investigating permeability, pore-volume or surface-area of porous materials
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/185—Measuring radiation intensity with ionisation chamber arrangements
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N15/00—Investigating characteristics of particles; Investigating permeability, pore-volume or surface-area of porous materials
- G01N2015/0007—Investigating dispersion of gas
- G01N2015/0015—Investigating dispersion of gas in solids
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Abstract
The invention provides a method and an experimental system for determining a tritium diffusion coefficient based on a release rate, wherein the experimental system comprises a gas carrying device, a heating furnace and a tritium online monitoring device; according to the method and the experimental system for determining the diffusion coefficient of tritium in the spherical porous medium material, the counting rate corresponding to the activity concentration of tritium at the detection position in the experimental system is obtained at a plurality of temperatures within a certain temperature range, the release rate of tritium released from the spherical sample to be detected under the temperature condition is obtained, the specific numerical value of the diffusion coefficient of tritium in the spherical sample to be detected under the temperature condition and the general expression of the diffusion coefficient of tritium in the spherical porous medium material within the corresponding temperature range are further obtained, and the diffusion coefficient of tritium in the porous medium material within the heating temperature range is determined.
Description
Technical Field
The invention relates to the technical field of reactor engineering, in particular to the field of pebble-bed high-temperature gas cooled reactors, and specifically relates to a method and an experimental system for determining a tritium diffusion coefficient based on a release rate.
Background
The High Temperature Gas-cooled Reactor (HTGR) and the Very High Temperature Gas-cooled Reactor (VHTR) prototyped therewith are the most commercially advanced reactors of the six Reactor types of the fourth generation nuclear power system. A Pebble Bed Modular High-Temperature gas-cooled reactor nuclear power plant project (HTR-PM) designed on the basis of a 10MW High-Temperature gas-cooled reactor (HTR-10) of the nuclear research institute of Qinghua university is honored and built in Shandong and enters the final debugging stage at present. One of the most important characteristics of a high temperature gas cooled reactor is the intrinsic safety characteristic. The intrinsic safety refers to that when the reactor is in an abnormal working condition, the reactor can be restored to a normal operation state or safely shut down only through the characteristics of the reactor without depending on external force, so that serious accidents such as the melting of the reactor core are fundamentally avoided.
The adoption of TRISO (structural-isotropic) coated granular fuel elements of all-ceramic type is one of the important reasons for the intrinsic safety characteristics of high-temperature gas cooled reactors. TRISO coated particles made of UO2The core, the loose pyrolytic carbon layer, the inner compact pyrolytic carbon layer, the silicon carbide layer and the outer compact pyrolytic carbon layer are uniformly dispersed in the graphite matrix and pressed by a quasi-cold isostatic pressing process to form the fuel element with the diameter of 6 cm. The pyrolytic carbon and silicon carbide layers of TRISO-coated particles and the graphite matrix in the spherical fuel element are largely retainedMost radioactive fission products include tritium.
Except that tritium generated by the ternary fission of the fissile nuclide in the fuel element is retained in a reactor core, Li-6 and Li-7 impurities in matrix graphite, a graphite reflecting layer and carbon bricks are activated, and a certain amount of tritium can still be generated by the activation of a main loop coolant He-3 and the activation of B-10 in absorption spheres, control rods and carbon bricks. A large amount of graphite exists in the reactor core, tritium generated in matrix graphite or structural graphite can diffuse from the graphite into helium in the primary loop at high temperature, and then permeate into the secondary loop or directly enter the environment along with the leakage of the helium in the primary loop, so that radioactive pollution to the secondary loop or the environment is caused. Tritium water generated by combining tritium and oxygen is difficult to distinguish from light water, and is difficult to remove once entering a biosphere. Considering the large contribution of tritium to public dose, tritium impact on the environment and public will be considered separately in the evaluation of nuclear facility environmental impact.
The tritium source item of the high-temperature gas cooled reactor is estimated to be the basis for evaluating the influence of tritium on the environment and the public. The diffusion process of tritium in fuel elements, matrix graphite and structural graphite is particularly important in determining the diffusion (permeation) coefficient of the key parameter therein. At present, most domestic measurement on the diffusion coefficient of tritium aims at various stainless steel materials, and experimental measurement and theoretical research on the diffusion coefficient of tritium in a graphite material are relatively few. Therefore, it is necessary to provide an effective and feasible method and experimental system for measuring the diffusion coefficient of tritium.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a method and an experimental system for determining a tritium diffusion coefficient based on a release rate, wherein the method and the experimental system obtain counting rates corresponding to activity concentrations of tritium at detection positions in the experimental system at a certain temperature range, and deduce the release rate of the tritium released from a spherical sample to be tested under the temperature condition, so as to obtain a specific numerical value of the diffusion coefficient of the tritium in the spherical sample to be tested under the temperature condition and a general expression of the diffusion coefficient of the tritium in the porous medium material within the corresponding temperature range, namely determine the diffusion coefficient of the porous medium material within the heating temperature range.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
a method for determining a tritium diffusion coefficient based on a release rate, the method comprising:
s1, heating a sample of the spherical porous medium material to enable tritium in the sample to be in HT or T state2And CH3T form is released by diffusion to release HT and T2And CH3T, cooling to a certain temperature;
s2, treating cooled HT and T2And CH3T carries out real-time on-line monitoring on tritium activity concentration to obtain a change curve of tritium release rate along with time T, and the tritium release rate released from the spherical porous medium material at a certain time T is ZR(t)[g/s]：
Wherein m is0Is the initial mass [ g ] of tritium in the spherical porous medium material sample at the beginning of the experiment]And R is the radius [ m ] of the spherical porous medium material sample]D is the diffusion coefficient [ m ]2/s]Where pi is a circumferential constant, and t is a time [ s ] corresponding to a measurement after the start of the experiment]；
The resulting release rate [ g/s ] was measured:
ZR(t)＝F·k(t),
wherein F is a correction coefficient [ g/count ], k is a detector count rate [ counts/s ];
wherein t isiFor measuring the starting moment s],tfFor measuring the end time s]，miRepresents the initial mass [ g ] of tritium in the spherical porous medium material sample before the measurement starts]，mfRepresents the mass [ g ] of tritium in the spherical porous medium material sample after the measurement is finished]；
S3, a series of time points t experimentally measured at a certain temperature and corresponding release rates ZR(t), i.e. a set of (t, Z)R(t)) data, using tritium release rate ZR(t) fitting the equation to obtain the optimal diffusion coefficient D value of tritium in the spherical porous medium material sample at the temperature,
s4, changing the heating temperature of the spherical porous medium material sample and repeating the process, obtaining a series of temperature values and corresponding measured values of the diffusion coefficient of tritium in the spherical porous medium material sample at the temperature, namely a group of (T, D) data, and then fitting by using an Arrhenius formula to obtain the key parameters of the general expression of the diffusion coefficient in the corresponding experimental temperature range: diffusion frequency factor D0[m2/s]And diffusion excitation energy Q [ J/mol [ ]]Determining a general expression of the diffusion coefficient of tritium in the spherical porous medium material within a corresponding temperature range;
wherein R isgIs an ideal gas constant with a value of 8.314[ J/(mol. K)]T is the temperature [ K ]]；
The diffusion coefficient expression determined by the spherical porous medium material sample is the expression of the diffusion coefficient of tritium in the porous medium material within the heating temperature range.
In some embodiments, the spherical porous media material is heated to a temperature of 300-1400 ℃.
In some embodiments, in step S1, HT, T are compared2And CH3And T, cooling to room temperature.
In some embodiments, HT, T after cooling2And CH3And the real-time online monitoring of tritium activity and concentration is carried out by a tritium online monitoring device.
Meanwhile, the invention also provides an experimental system for implementing the method for determining the tritium diffusion coefficient based on the release rate, which is characterized by comprising the following steps:
a carrier gas device;
heating furnace;
and a tritium on-line monitoring device;
the tritium online monitoring device is characterized in that the tritium online monitoring device is connected with the heating furnace through a pipeline, wherein the gas carrying device is connected with one end of the heating furnace through a pipeline, and the other end of the heating furnace is connected with the tritium online monitoring device through a pipeline.
In some embodiments, the cooling device is disposed on a conduit between the furnace and the online tritium monitoring device.
In some embodiments, the experimental system still includes tail gas recovery unit, tail gas recovery unit includes check valve, stop valve, pressure gauge and waste gas holding vessel, the waste gas holding vessel is linked together through pipeline and tritium on-line monitoring device's gas outlet, the pressure gauge is installed waste gas holding vessel air inlet department, check valve and stop valve are in proper order the series installation on the pipeline.
In some embodiments, the detector used in the tritium online monitoring device is an ionization chamber or a proportional counter.
The invention has the beneficial effects that: according to the method and the experimental system for determining the diffusion coefficient of tritium based on the release rate, the counting rate corresponding to the activity concentration of tritium at the detection position in the experimental system is obtained at a plurality of temperatures within a certain temperature range, the release rate of tritium released from the spherical sample to be detected under the temperature condition is obtained, and further the specific numerical value of the diffusion coefficient of tritium in the spherical sample to be detected under the temperature condition and the general expression of the diffusion coefficient of tritium in the spherical porous medium material within the corresponding temperature range are obtained, namely the diffusion coefficient of tritium within the heating temperature range in the porous medium material is determined.
Drawings
FIG. 1 is a schematic diagram of the structural principle of the experimental system in the present invention.
Detailed Description
The invention is described in further detail below with reference to the drawings and the detailed description.
The invention provides a method and an experimental system for determining a tritium diffusion coefficient based on a release rate, aiming at the fact that in the existing high-temperature gas cooled reactor source item analysis, the diffusion coefficient is the most important parameter in the process of researching the transport of tritium in graphite, but the theoretical research and the experimental results of the diffusion coefficient of tritium in a porous medium material are relatively lacked at present.
First, the present invention provides a method for determining a tritium diffusion coefficient based on a release rate, for convenience of description, a graphite material in a porous medium material is taken as an example for description, and the following method and experimental system can be applied to other porous medium materials, without limitation. The method comprises the following steps:
s1, heating and irradiating graphite spheres or other spherical graphite materials at a certain temperature (in the embodiment, the temperature is 300-1400 ℃), so that tritium in the graphite spheres or other spherical graphite materials is treated by HT and T2And CH3T form is released by diffusion to release HT and T2And CH3T is cooled to a certain temperature (about 25 ℃ in the present example),
s2, treating cooled HT and T2And CH3And T, carrying out real-time online monitoring on the tritium activity concentration to obtain a change curve of the tritium release rate along with time T.
The release rate of tritium released from the graphite nodule at a certain time t is ZR(t)[g/s]：
Wherein m is0Is the initial mass of tritium in the graphite nodule sample at the beginning of the experiment [ g]R is the radius [ m ] of the graphite nodule sample]D is the diffusion coefficient [ m ]2/s]Where pi is a circumferential constant, and t is a time [ s ] corresponding to a measurement after the start of the experiment]；
The resulting release rate [ g/s ] was measured:
ZR(t)＝F·k(t),
wherein F is a correction coefficient [ g/count ], and k is a counting rate [ counts/s ] of the detector at the time t;
wherein t isiFor measuring the starting moment s],tfFor measuring the end time s]，miDenotes the initial mass of tritium in the graphite nodule sample [ g ] before the start of the measurement]，mfDenotes the mass of tritium [ g ] in the graphite nodule sample after the measurement]；
S3, a series of time points t experimentally measured at a certain temperature and corresponding release rates ZR(t), i.e. a set of (t, Z)R(t)) data, using tritium release rate ZR(t) fitting a formula to obtain the optimal diffusion coefficient D value of tritium in the graphite nodule at the temperature;
s4, changing the heating temperature of the graphite ball and repeating the above process to obtain a series of temperature values and specific values of the diffusion coefficient of tritium in the graphite ball corresponding to the temperature values, namely a group of (T, D) data, and fitting by using an Arrhenius formula (as follows) to obtain the key parameters of the general expression of the diffusion coefficient in the corresponding experimental temperature range: diffusion frequency factor D0[m2/s]And diffusion excitation energy Q [ J/mol [ ]]Namely, a general expression of the diffusion coefficient of tritium in the graphite nodule in the corresponding temperature range is determined.
Wherein R isgIs an ideal gas constant with a value of 8.314[ J/(mol. K)]T is the temperature [ K ]]。
As can be understood from the above formula, the release rate Z obtained by measurementR(t), the specific value of the diffusion coefficient D of tritium in the graphite nodule irradiated by the high-temperature gas cooled reactor at the temperature can be deduced reversely. Several different temperature points (e.g., 10) are selected within the temperature range of interest, e.g., 300-Measuring the diffusion coefficient to obtain a series of combinations of temperature T and corresponding diffusion coefficient D, and using the Arrhenius formula
The key parameters of the general expression of the diffusion coefficient can be determined: diffusion frequency factor D0[m2/s]And diffusion excitation energy Q [ J/mol [ ]]Namely, a general expression of the diffusion coefficient D of tritium in the irradiated graphite nodule in the corresponding temperature range is determined. The diffusion coefficient determined in the spherical porous sample is the diffusion coefficient in the porous medium material, namely the diffusion coefficient is the inherent property of the material and is irrelevant to the shape of the material, and the diffusion coefficient of tritium in the porous medium material within the heating temperature range is determined by measuring the diffusion coefficient of the spherical porous medium sample.
By adopting the experimental method and the system, the release rate of tritium in a sample to be tested can be measured quickly and in real time, a change curve of the release rate of tritium at a certain temperature along with time t can be obtained in a short time, experimental data can be more, and higher precision can be realized for fitting a diffusion coefficient through the release rate subsequently.
Referring to fig. 1, the present embodiment further provides an experimental system for implementing the method for determining a tritium diffusion coefficient based on a release rate, where the experimental system includes a carrier gas device 1, a heating furnace 7, and an online tritium monitoring device 14. The carrier gas unit 1 may typically employ a helium gas source carrying tritium released from the sample to be tested to the subsequent on-line monitoring unit section. The gas outlet of the carrier gas device 1 is connected with one end of a heating furnace 7 through a pipeline 3, the heating furnace 7 heats helium entering the pipeline 3, the heating furnace 7 has the functions of heating the porous tritium-containing medium material to a required temperature and maintaining the porous tritium-containing medium material at a stable certain temperature for carrying out a tritium release experiment, generally, the temperature range is 300-1400 ℃, and a thermometer 8 is arranged on the heating furnace 7 to monitor the working temperature of the heating furnace 7. A stop valve 2, a pressure gauge 4, a mass flow meter 5, and a stop valve 6 are provided in this order on the pipe 3 between the carrier gas device 1 and the heating furnace 7. The other end of the heating furnace 7 is connected to one end of the cooling device 11 through a pipe 3, and a pair of stop valves 9 and 10 are provided between the two pipes 3. The other end of the cooling device 11 is connected with one end of the tritium online monitoring device 14 through the pipeline 3, the cooling device 11 is used for cooling helium gas heated by the heating furnace 7, the thermometer 12 is installed on the cooling device 11, the cooled tritium-containing helium gas is measured, the temperature of the cooled tritium-containing helium gas is reduced to normal temperature (about 25 ℃), and damage to the tritium online monitoring device 14 caused by the high-temperature helium gas is prevented (in the embodiment, an ionization chamber or a proportional counter is preferentially adopted by a detector of the tritium online monitoring device). The other end of the tritium online monitoring device 14 is connected with a tail gas recovery device 20. The tritium on-line monitoring device 14 measures the rate of tritium release by the radioactivity of tritium when in use. A stop valve 15 is also arranged between the tritium online monitoring device 14 and the tail gas recovery device 20. Tail gas recovery unit 20 includes check valve 16, stop valve 17, pressure gauge 18 and exhaust gas storage tank 19, and exhaust gas storage tank 19 is linked together through pipeline and tritium on-line monitoring device 14's gas outlet, and pressure gauge 18 is installed in 19 air inlet departments of exhaust gas storage tank, and check valve 16 and stop valve 17 are established ties in proper order and are installed on the pipeline. The exhaust gas storage tank 19 is used for storing tritium-containing exhaust gas for subsequent treatment during the experiment.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations.
Claims (8)
1. A method for determining a tritium diffusion coefficient based on a release rate, the method comprising:
s1, heating a sample of the spherical porous medium material to enable tritium in the sample to be in HT or T state2And CH3T form is released by diffusion to release HT and T2And CH3T, cooling to a certain temperature;
s2, treating cooled HT and T2And CH3T, carrying out real-time on-line monitoring on the tritium activity concentration to obtain a change curve of the tritium release rate along with time T,the release rate of tritium released from the spherical porous medium material at a certain time t is ZR(t)[g/s]：
Wherein m is0Is the initial mass [ g ] of tritium in the spherical porous medium material sample at the beginning of the experiment]And R is the radius [ m ] of the spherical porous medium material sample]D is the diffusion coefficient [ m ]2/s]Where pi is a circumferential constant, and t is a time [ s ] corresponding to a measurement after the start of the experiment]；
The resulting release rate [ g/s ] was measured:
ZR(t)＝F·k(t),
wherein F is a correction coefficient [ g/count ], and k is a counting rate [ counts/s ] of the detector at the time t;
wherein t isiFor measuring the starting moment s],tfFor measuring the end time s]，miRepresents the initial mass [ g ] of tritium in the spherical porous medium material sample before the measurement starts]，mfRepresents the mass [ g ] of tritium in the spherical porous medium material sample after the measurement is finished]；
S3, a series of time points t experimentally measured at a certain temperature and corresponding release rates ZR(t), i.e. a set of (t, Z)R(t)) data, using tritium release rate ZR(t) fitting the equation to obtain the optimal diffusion coefficient D value of tritium in the spherical porous medium material sample at the temperature,
s4, changing the heating temperature of the spherical porous medium material sample and repeating the process, obtaining a series of temperature values and corresponding measured values of the diffusion coefficient of tritium in the spherical porous medium material sample at the temperature, namely a group of (T, D) data, and then fitting by using an Arrhenius formula to obtain the key parameters of the general expression of the diffusion coefficient in the corresponding experimental temperature range: diffusion frequency factor D0[m2/s]And diffusion excitation energy Q [ J/mol [ ]]Determining a general expression of the diffusion coefficient of tritium in the spherical porous medium material within a corresponding temperature range;
wherein R isgIs an ideal gas constant with a value of 8.314[ J/(mol. K)]T represents a temperature [ K ]]；
The diffusion coefficient expression determined by the spherical porous medium material sample is the expression of the diffusion coefficient of tritium in the porous medium material within the heating temperature range.
2. The method for determining the tritium diffusion coefficient based on the release rate as claimed in claim 1, wherein the heating temperature of the spherical porous medium material is 300-1400 ℃.
3. A method for determining tritium diffusion coefficient based on release rate according to claim 1 or 2, characterized in that in step S1, HT, T2And CH3And T, cooling to room temperature.
4. A method for tritium diffusion coefficient determination based on release rate according to claim 1, 2 or 3, characterized by HT, T after cooling2And CH3And the real-time online monitoring of tritium activity and concentration is carried out by a tritium online monitoring device.
5. An experimental system for implementing a method for determining a tritium diffusion coefficient based on a release rate according to claim 1, characterized in that it comprises:
a carrier gas device;
heating furnace;
and a tritium on-line monitoring device;
the tritium online monitoring device is characterized in that the tritium online monitoring device is connected with the heating furnace through a pipeline, wherein the gas carrying device is connected with one end of the heating furnace through a pipeline, and the other end of the heating furnace is connected with the tritium online monitoring device through a pipeline.
6. The experimental system of claim 5, further comprising a cooling device disposed on a conduit between the furnace and the tritium online monitoring device.
7. The experimental system of claim 6, further comprising a tail gas recovery device, wherein the tail gas recovery device comprises a check valve, a stop valve, a pressure gauge and a waste gas storage tank, the waste gas storage tank is communicated with a gas outlet of the tritium online monitoring device through a pipeline, the pressure gauge is installed at a gas inlet of the waste gas storage tank, and the check valve and the stop valve are sequentially installed on the pipeline in series.
8. The experimental device according to claim 5, wherein the detector adopted by the tritium online monitoring device is an ionization chamber or a proportional counter.
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Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| SU702836A1 (en) * | 1978-04-24 | 1981-03-23 | Предприятие П/Я Г-4665 | Method of determining diffusion coefficient of beta-active gases in solid materials |
| CN105928855A (en) * | 2016-04-20 | 2016-09-07 | 中国原子能科学研究院 | Measuring apparatus and method for surface micropressure tritium absorption rate constant of material |
| CN105928854A (en) * | 2016-04-20 | 2016-09-07 | 中国原子能科学研究院 | Apparatus for controllable micropressure tritium adsorption and on-line testing of concentration and depth distribution of tritium in material |
| CN106018003A (en) * | 2016-05-20 | 2016-10-12 | 中国科学院上海应用物理研究所 | Sampling device and measurement method for multi-form tritium in atmosphere around nuclear facility |
| CN106501125A (en) * | 2016-12-13 | 2017-03-15 | 清华大学 | Gas absorption desorption test device and method of testing |
| CN109031390A (en) * | 2018-05-31 | 2018-12-18 | 拓世氢源（深圳）科技有限公司 | It is a kind of complexity gaseous environment in different shape tritium monitoring method |
| CN110954939A (en) * | 2019-12-24 | 2020-04-03 | 中国原子能科学研究院 | Tritium monitor laboratory calibrating device |
-
2020
- 2020-12-30 CN CN202011619246.9A patent/CN112881238B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| SU702836A1 (en) * | 1978-04-24 | 1981-03-23 | Предприятие П/Я Г-4665 | Method of determining diffusion coefficient of beta-active gases in solid materials |
| CN105928855A (en) * | 2016-04-20 | 2016-09-07 | 中国原子能科学研究院 | Measuring apparatus and method for surface micropressure tritium absorption rate constant of material |
| CN105928854A (en) * | 2016-04-20 | 2016-09-07 | 中国原子能科学研究院 | Apparatus for controllable micropressure tritium adsorption and on-line testing of concentration and depth distribution of tritium in material |
| CN106018003A (en) * | 2016-05-20 | 2016-10-12 | 中国科学院上海应用物理研究所 | Sampling device and measurement method for multi-form tritium in atmosphere around nuclear facility |
| CN106501125A (en) * | 2016-12-13 | 2017-03-15 | 清华大学 | Gas absorption desorption test device and method of testing |
| CN109031390A (en) * | 2018-05-31 | 2018-12-18 | 拓世氢源（深圳）科技有限公司 | It is a kind of complexity gaseous environment in different shape tritium monitoring method |
| CN110954939A (en) * | 2019-12-24 | 2020-04-03 | 中国原子能科学研究院 | Tritium monitor laboratory calibrating device |
Non-Patent Citations (6)
| Title |
|---|
| KEN-ICHI HASHIZUME 等: "Measurement of Diffusion Coefficient of Tritium in Alpha-Phase of Zirconium Based on Glow Discharge Implantation Method", 《FUSION TECHNOLOGY》 * |
| KENJIOKUNO 等: "Tritium diffusivity in lithium-based ceramic breeders irradiated with neutrons", 《FUSION ENGINEERING AND DESIGN》 * |
| MAKOTO KOBAYASHI 等: "Release kinetics of tritium generated in lithium-enriched Li2+xTi〇3 by thermal neutron irradiation", 《FUSION ENGINEERING AND DESIGN》 * |
| YI KANG 等: "In-reactor experiment and the tritium diffusion coefficient in molten lithium-tin alloy", 《JOURNAL OF NUCLEAR MATERIALS》 * |
| 李仁顺 等: "氦在材料中基于扩散机理的热释放特征", 《物理学报》 * |
| 肖成建 等: "LiA102陶瓷小球的堆外放氚行为", 《强激光与粒子束》 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113945669A (en) * | 2021-10-14 | 2022-01-18 | 安徽亚格盛电子新材料有限公司 | Trimethyl gallium online analysis device and analysis method thereof |
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