CN112816263A - Device and method for measuring trace suspended solids in water of nuclear power plant - Google Patents
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 114
- 239000007787 solid Substances 0.000 title claims abstract description 77
- 238000000034 method Methods 0.000 title claims abstract description 48
- 239000012528 membrane Substances 0.000 claims abstract description 42
- 238000005070 sampling Methods 0.000 claims abstract description 15
- 230000002572 peristaltic effect Effects 0.000 claims abstract description 12
- 239000012466 permeate Substances 0.000 claims abstract description 7
- SZVJSHCCFOBDDC-UHFFFAOYSA-N ferrosoferric oxide Chemical compound O=[Fe]O[Fe]O[Fe]=O SZVJSHCCFOBDDC-UHFFFAOYSA-N 0.000 claims description 41
- JEIPFZHSYJVQDO-UHFFFAOYSA-N iron(III) oxide Inorganic materials O=[Fe]O[Fe]=O JEIPFZHSYJVQDO-UHFFFAOYSA-N 0.000 claims description 17
- 239000011148 porous material Substances 0.000 claims 1
- 238000005259 measurement Methods 0.000 abstract description 19
- 238000001514 detection method Methods 0.000 abstract description 16
- 238000005059 solid analysis Methods 0.000 abstract description 4
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 11
- 239000000126 substance Substances 0.000 description 11
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 8
- 229910052705 radium Inorganic materials 0.000 description 8
- HCWPIIXVSYCSAN-UHFFFAOYSA-N radium atom Chemical compound [Ra] HCWPIIXVSYCSAN-UHFFFAOYSA-N 0.000 description 8
- 238000004458 analytical method Methods 0.000 description 6
- 230000007797 corrosion Effects 0.000 description 6
- 238000005260 corrosion Methods 0.000 description 6
- 238000001035 drying Methods 0.000 description 6
- 239000002245 particle Substances 0.000 description 5
- 239000002826 coolant Substances 0.000 description 4
- 229910052742 iron Inorganic materials 0.000 description 4
- 238000012544 monitoring process Methods 0.000 description 4
- 229910052759 nickel Inorganic materials 0.000 description 4
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 3
- 239000000428 dust Substances 0.000 description 3
- 238000001914 filtration Methods 0.000 description 3
- 239000011261 inert gas Substances 0.000 description 3
- 239000011630 iodine Substances 0.000 description 3
- 229910052740 iodine Inorganic materials 0.000 description 3
- 230000002285 radioactive effect Effects 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000011085 pressure filtration Methods 0.000 description 2
- 239000000047 product Substances 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 239000000443 aerosol Substances 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 239000003086 colorant Substances 0.000 description 1
- 238000004737 colorimetric analysis Methods 0.000 description 1
- 239000013078 crystal Substances 0.000 description 1
- 230000008021 deposition Effects 0.000 description 1
- 239000007769 metal material Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 150000003255 radium Chemical class 0.000 description 1
- 238000002791 soaking Methods 0.000 description 1
- 230000009897 systematic effect Effects 0.000 description 1
- 229910021654 trace metal Inorganic materials 0.000 description 1
- 238000005303 weighing Methods 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
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/02—Devices for withdrawing samples
- G01N1/10—Devices for withdrawing samples in the liquid or fluent state
- G01N1/14—Suction devices, e.g. pumps; Ejector devices
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/28—Preparing specimens for investigation including physical details of (bio-)chemical methods covered elsewhere, e.g. G01N33/50, C12Q
- G01N1/34—Purifying; Cleaning
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N21/00—Investigating or analysing materials by the use of optical means, i.e. using sub-millimetre waves, infrared, visible or ultraviolet light
- G01N21/01—Arrangements or apparatus for facilitating the optical investigation
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N21/00—Investigating or analysing materials by the use of optical means, i.e. using sub-millimetre waves, infrared, visible or ultraviolet light
- G01N21/17—Systems in which incident light is modified in accordance with the properties of the material investigated
- G01N21/25—Colour; Spectral properties, i.e. comparison of effect of material on the light at two or more different wavelengths or wavelength bands
- G01N21/29—Colour; Spectral properties, i.e. comparison of effect of material on the light at two or more different wavelengths or wavelength bands using visual detection
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- Life Sciences & Earth Sciences (AREA)
- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- General Physics & Mathematics (AREA)
- Chemical & Material Sciences (AREA)
- Analytical Chemistry (AREA)
- Biochemistry (AREA)
- General Health & Medical Sciences (AREA)
- Immunology (AREA)
- Pathology (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Hydrology & Water Resources (AREA)
- Engineering & Computer Science (AREA)
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- Molecular Biology (AREA)
- Sampling And Sample Adjustment (AREA)
Abstract
The invention provides a device for measuring trace suspended solids in water of a nuclear power plant, and belongs to the technical field of solid matter content measurement. The invention relates to a device for measuring trace suspended solids in water of a nuclear power plant, which comprises a pressure container, a peristaltic pump and a filter which are sequentially connected, wherein a filter screen paved with a filter membrane is arranged in the filter. A method for measuring trace suspended solids in water of a nuclear power plant based on the foregoing, comprising the following steps: (1) measuring a water sample to be measured and putting the water sample into a pressure container; (2) opening a peristaltic pump to force the water sample to permeate the filter membrane in a positive pressure mode; (3) after all water samples are filtered, taking out the filter membrane; (4) and (3) after the filter membrane absorbs water and is dried at normal temperature, comparing the color of the filter membrane with a colorimetric card, and determining the concentration of the water sample and the type of suspended solids in the water sample. The invention has small sampling amount, and can reach the minimum detection limit of 10 mug/kg only by 1L of water sample; when the suspended solid analysis is carried out on a sample with radioactivity, the contact time of a person and the sample is shortened.
Description
Technical Field
The invention belongs to the technical field of solid matter content measurement, and particularly relates to a device for measuring trace suspended solids in water of a nuclear power plant.
Background
The primary water system, the secondary water system and the closed water system of the pressurized water reactor nuclear power station have strict control on water quality, and the main purpose of the system is to relieve the corrosion of iron and nickel metal materials and avoid a series of problems of corrosion product deposition, corrosion damage, radioactivity level increase and the like caused by the corrosion. The suspended solid is one of important parameters for monitoring the water quality of a pressurized water reactor nuclear power station, and the main source of the suspended solid is a trace metal corrosion product in a system. When the content of suspended solids in water rises, chemical staff can be prompted that the corrosion condition is aggravated, and measures should be taken in time to avoid the occurrence of related accidents.
The invention discloses a solid radium source central point measuring instrument and a detection method thereof, and belongs to the technical field of nuclear and radiation environment monitoring and measuring, in particular to the solid radium source central point measuring instrument and the detection method thereof, aiming at providing equipment capable of realizing position measurement of the solid radium source central point and quality detection of an internal source tube, a related measuring device and a monitoring method thereof. The device comprises a host (1), a detector (2), a shielding body (4) and an automatic measuring frame (5). The method comprises the steps of measurement, solid radium source position judgment and radium source internal pipe damage and leakage judgment. The invention adopts the shielding body 4 with the collimating slit, and can realize the position measurement of the central point of the solid radium source and the quality detection of the internal source tube. By carrying out measurement, the position distribution of radioactive 'hot spots' (radium salt powder) in the solid radium source can be accurately measured; whether the source pipe in the solid radium source is damaged or leaked can be accurately judged.
The invention belongs to the technical field of monitoring of integrity of a pressure boundary of a primary loop of a nuclear power plant reactor, and particularly relates to a system and a method for quantitatively measuring the leakage rate of a primary loop coolant of a pressurized water reactor nuclear power plant. The system comprises a sampling loop, an F-18 particle detection device, a dust and iodine filter, an inert gas detection device, a control and measurement device and a suction pump; the sampling loop samples from the containment and is sequentially connected with an F-18 particle detection device, a dust and iodine filter, an inert gas detection device and an air pump; the control and measurement device respectively collects temperature and pressure signals of the sampling loop, measurement signals of the F-18 particle detection device, flow signals of a pipeline between the F-18 particle detection device and the dust and iodine filter, and measurement signals of the inert gas detection device. The leakage rate of the coolant of the primary loop of the reactor of the nuclear power plant is quantitatively measured by measuring 0.511MeV specific energy gamma rays generated by annihilation of beta + rays decayed by aerosol particles F-18 in the atmosphere of the containment.
There are two main methods for determining suspended solids:
the first is transmission method, the principle is to irradiate the sample with light of certain intensity, the suspended solid in water will reflect or scatter the light, the higher the content of suspended solid, the stronger the reflection and scattering, the weaker the transmitted light, draw a linear curve through the standard sample, and the suspended solid content can be obtained by the reverse calculation of the intensity of the transmitted light of the sample. The disadvantage of this method is the limited detection capacity and the inability to achieve the determination of trace amounts (μ g/kg grade) of suspended solids.
The other is a gravimetric method and is also a common measuring method of nuclear power stations. The principle is that suspended solids in water are filtered by using a filter membrane with the aperture of 0.45 mu m, then the filter membrane is dried and weighed, and after the mass of the filter membrane is deducted, the concentration value of the suspended solids can be calculated by the filtered water amount. The method mainly has the following problems in the application process:
1) the sampling amount is large. Taking the case that the control limit value of suspended solids in a primary water system of a nuclear power plant is less than or equal to 50 mug/kg, the method is limited to the measurement precision (0.1 mg) of an analytical balance, and at least 20L of water needs to be taken by adopting a gravimetric method for measuring. A two-loop water system (less than or equal to 10 mu g/kg) with stricter control on suspended solids is adopted, and the water intake amount is higher than 100L;
2) the analysis process is complicated and the analysis time is long. The gravimetric method for determining the suspended solid relates to the processes of filter membrane soaking, filter membrane drying, filter membrane constant weight, sample filtration, sample drying, sample weighing and the like, and the average time for analyzing the suspended solid for one time is 3 hours.
3) Personnel receive high radioactive doses. Due to the large sampling amount and long analysis time, when the radioactive sample is analyzed by adopting a gravimetric method, an analyst is subjected to higher dose, and the radiation dose of 3-10 MuSv is generated each time when a nuclear power station analyzes a primary circuit coolant sample as an example.
Disclosure of Invention
In view of the above, the invention provides a device and a method for measuring trace suspended solids in water of a nuclear power plant, the invention has small sampling amount, the lowest detection limit of 10 mug/kg can be reached only by 1L of water sample, the impact of large sampling amount on the water filling amount of the system is avoided, and the workload of sampling personnel is also reduced; when the suspended solid analysis is carried out on a sample with radioactivity, the contact time between a person and the sample is shortened, and the working dose is greatly reduced, for example, when a primary circuit coolant sample is analyzed by a certain nuclear power station, the single dose is less than 1 mu Sv.
The invention relates to a device for measuring trace suspended solids in water of a nuclear power plant, which comprises a sample container, a peristaltic pump and a filter which are sequentially connected, wherein a filter screen paved with a filter membrane is arranged in the filter. The aperture of the filter membrane is less than or equal to 0.45 μm.
The main components of the suspended solids in the water of the nuclear power plant are iron-based oxide and nickel-based oxide which are colored substances, and the color of the filtered and enriched oxide in the water is related to the type of the oxide, so the color depth of the filtered and enriched oxide in the water is in direct proportion to the concentration of the oxide. Therefore, the content of the solid matters in the water and the types of the solid matters can be judged by enriching the solid matters in the water of the nuclear power plant and observing the color.
A method for measuring trace suspended solids in water of a nuclear power plant based on the foregoing, comprising the following steps:
(1) measuring a water sample to be measured and putting the water sample into a sample container;
(2) opening a peristaltic pump to force the water sample to permeate the filter membrane in a positive pressure mode;
(3) after all water samples are filtered, taking out the filter membrane;
(4) and (3) placing the filter membrane on a paper towel to absorb water, drying for 5 minutes at room temperature, wherein the room temperature is 25-30 ℃, so that the solid matters can be prevented from being decomposed, or the crystal water is evaporated to influence the color on the final filter paper, comparing the color of the filter membrane with a colorimetric card, and determining the concentration of the water sample and the type of the suspended solids in the water sample.
Preferably, the concentration on the color chart is in the range of 10-1000 mug/kg.
The types on the color comparison card comprise Fe3O4、Fe2O3·Fe3O4·NiO、Fe2O3H2O color comparison card. Said Fe2O3·Fe3O4Fe in NiO Compound2O3：Fe3O4: the ratio of NiO is 2:1:3 or 1:2:3 or 1:4: 5. The sampling volume of the water sample to be detected is 1L.
Wherein, Fe3O4R = G = B in RGB value of the color chart, R ranges from 250 to 70, and corresponding Fe3O4The concentration range of (A) is 10-1000. mu.g/kg.
Different concentrations of Fe2O3·Fe3O4NiO and Fe2O3·H2O corresponds to different colors on the color chart.
Meanwhile, the color comparison cards of Fe2O 3. Fe3O 4. NiO with different concentrations have different RGB values, Fe2O 3: fe3O 4: NiO also has different RGB values when the ratio is 2:1:3 or 1:2:3 or 1:4: 5.
Fe2O3·H2Different concentrations on the O color card correspond to different RGB values.
The specific RGB values are as follows:
the invention mainly aims to judge whether the content of suspended solid matters in water of a nuclear power plant exceeds the standard, but if further requirements exist, the content of the solid matters is required to be determined, and a color comparison card can be prepared in advance according to the requirements. And judging whether the approximate concentration of the solid matter exceeds the range according to the color shade and the color characteristics on the color comparison card. The method can not accurately measure the content of the solid matters, but can be used as an important judgment method for judging whether the solid matters in the water of the nuclear power plant exceed the standard or not.
The method utilizes iron-based oxides and nickel-based oxides which are colored substances, the depth of the color of the oxides in water after being filtered and enriched is in direct proportion to the concentration of the oxides in water, and the content of the solid substances in the water and the types of the solid substances are judged by enriching the solid substances in the water of the nuclear power plant and observing the color. The invention has the following beneficial effects: 1) the sampling amount is small, the minimum detection limit of 10 mug/kg can be reached only by 1L of water sample, the impact of large sampling amount on the water filling amount of the system is avoided, and the workload of sampling personnel is also reduced; 2) the operation process only needs four steps, and is simple and easy to implement. Meanwhile, positive pressure filtration is adopted, the whole process only needs 20 minutes, and the analysis time is greatly shortened; 3) when the suspended solid analysis is carried out on the sample with radioactivity, the contact time between a person and the sample is shortened, and the working dose is greatly reduced. The method effectively improves the efficiency and safety of the determination of the trace suspended solids in the water system of the nuclear power station.
Drawings
Fig. 1 is a schematic structural diagram of a measurement apparatus for measuring a trace amount of suspended solids in water of a nuclear power plant according to an embodiment of the present invention.
Wherein; 1. a sample container; 2. a peristaltic pump; 3. a filter; 4. filtering with a screen; .
Detailed Description
The present invention will be described in detail with reference to specific embodiments.
Example 1
Referring to fig. 1, fig. 1 is a schematic structural diagram of a measurement apparatus for measuring trace suspended solids in water of a nuclear power plant. The utility model provides a measuring equipment of trace suspended solid in nuclear power plant aquatic, includes sample container 1, peristaltic pump 2, the filter 3 that connects gradually, set up the filter screen 4 of having laid the filter membrane in the filter 3, sample container. The aperture of the filter membrane is less than or equal to 0.45 μm.
Basic principle of solid matter content measurement. The main components of the suspended solids in the water of the nuclear power plant are iron-based oxide and nickel-based oxide which are colored substances, and the color of the filtered and enriched oxide in the water is related to the type of the oxide, so the color depth of the filtered and enriched oxide in the water is in direct proportion to the concentration of the oxide. Therefore, the content of the solid matters in the water and the types of the solid matters can be judged by enriching the solid matters in the water of the nuclear power plant and observing the color.
Before the measurement is performed, the colorimetric card should be selected in advance.
A method for measuring trace suspended solids in water of a nuclear power plant based on the foregoing, comprising the following steps:
(1) measuring 1L of water sample 1 to be measured and putting the water sample into a sample container 1;
(2) opening a peristaltic pump 2 to force the water sample to permeate the filter membrane in a positive pressure mode;
(3) after all water samples are filtered, taking out the filter membrane;
(4) and after the filter membrane is dried, comparing the color of the filter membrane with a colorimetric card, and determining the concentration of the water sample and the type of suspended solids in the water sample.
Preferably, the concentration on the color chart is in the range of 10-1000 mug/kg. The types on the color comparison card comprise Fe3O4、Fe2O3·Fe3O4·NiO、Fe2O3·H2And (4) an O color comparison card. Said Fe2O3·Fe3O4Fe in NiO Compound2O3：Fe3O4: the ratio of NiO is 2:1:3 or 1:2:3 or 1:4: 5.
Wherein, Fe3O4R = G = B in RGB value of the color chart, R ranges from 250 to 70, and corresponding Fe3O4The concentration range of (A) is 10-1000. mu.g/kg.
Meanwhile, the content of the solid suspended substances is measured by adopting a gravimetric method.
Example 2
Before the measurement is performed, the colorimetric card should be selected in advance.
A method for measuring trace suspended solids in water of a nuclear power plant comprises the following steps:
(1) measuring 1L of water sample 2 to be measured and putting the water sample into a sample container 1;
(2) opening a peristaltic pump 2 to force the water sample to permeate the filter membrane in a positive pressure mode;
(3) after all water samples are filtered, taking out the filter membrane;
(4) drying the filter membrane, comparing the color of the filter membrane with a colorimetric card to determine the concentration of the water sample,
and the type of suspended solids in the water sample.
The types on the color comparison card comprise Fe3O4、Fe2O3·Fe3O4·NiO、Fe2O3·H2And (4) an O color comparison card. Said Fe2O3·Fe3O4Fe in NiO Compound2O3：Fe3O4: the ratio of NiO is 2:1:3 or 1:2:3 or 1:4: 5.
Wherein, Fe3O4R = G = B in RGB value of the color chart, R ranges from 250 to 70, and corresponding Fe3O4The concentration range of (A) is 10-1000. mu.g/kg.
Meanwhile, the content of the solid suspended substances is measured by adopting a gravimetric method.
Example 3
Before the measurement is performed, the colorimetric card should be selected in advance.
A method for measuring trace suspended solids in water of a nuclear power plant comprises the following steps:
(1) measuring 1L of a water sample 3 to be measured and putting the water sample into a sample container 1;
(2) opening a peristaltic pump 2 to force the water sample to permeate the filter membrane in a positive pressure mode;
(3) after all water samples are filtered, taking out the filter membrane;
(4) and after the filter membrane is dried, comparing the color of the filter membrane with a colorimetric card, and determining the concentration of the water sample and the type of suspended solids in the water sample.
Preferably, the concentration on the color chart is in the range of 10-1000 mug/kg.
The types on the color comparison card comprise Fe3O4、Fe2O3·Fe3O4·NiO、Fe2O3·H2And (4) an O color comparison card.
Meanwhile, the content of the solid suspended substances is measured by adopting a gravimetric method.
Example 4
Before the measurement is performed, the colorimetric card should be selected in advance.
A method for measuring trace suspended solids in water of a nuclear power plant comprises the following steps:
(1) measuring 1L of a water sample 4 to be measured and putting the water sample into a sample container 1;
(2) opening a peristaltic pump 2 to force the water sample to permeate the filter membrane in a positive pressure mode;
(3) after all water samples are filtered, taking out the filter membrane;
(4) placing the filter membrane on a paper towel for absorbing water, drying at room temperature for 5 minutes, drying the filter membrane, and then filtering the filter membrane
Comparing the color with a colorimetric card, and determining the concentration of the water sample and the type of suspended solids in the water sample.
Meanwhile, the content of the solid suspended substances is measured by adopting a gravimetric method.
Example 5
The procedure in example 5 was the same as in example 4, except that water was taken out differently.
Example 6
The procedure in example 6 was the same as in example 4 except that water was taken out differently.
Example 7
The procedure in example 7 was the same as in example 4 except that water was taken out differently.
The following measurements were obtained;
as can be seen by comparison, the analysis result of the colorimetric method is basically the same as that of the gravimetric method, and the water quality supervision requirement of the nuclear power station is met.
The invention, 1) the sample volume is small, only need 1L water sample can reach the lowest detection limit of 10 mug/kg, has avoided the impact of the large sample volume to the systematic water charge, has lightened the work burden of the sampling personnel too; 2) the operation process only needs four steps, and is simple and easy to implement. Meanwhile, positive pressure filtration is adopted, the whole process only needs 20 minutes, and the analysis time is greatly shortened; 3) when the suspended solid analysis is carried out on the sample with radioactivity, the contact time between a person and the sample is shortened, and the working dose is greatly reduced. The method effectively improves the efficiency and safety of the determination of the trace suspended solids in the water system of the nuclear power station.
The present invention is not limited to the above-described specific embodiments, and various modifications and variations are possible. Any modifications, equivalents, improvements and the like made to the above embodiments in accordance with the technical spirit of the present invention should be included in the scope of the present invention.
Claims (8)
1. The utility model provides a measuring equipment of trace suspended solid in nuclear power plant aquatic which characterized in that, is including pressure vessel, peristaltic pump, the filter that connects gradually, set up the filter screen of having laid the filter membrane in the filter.
2. The apparatus for measuring the amount of suspended solids in trace amounts in water of nuclear power plants as claimed in claim 1, wherein the pore size of said filter membrane is less than or equal to 0.45 μm.
3. A method for measuring trace suspended solids in water of a nuclear power plant based on any one of claims 1 to 2, which is characterized by comprising the following steps:
measuring a water sample to be measured and putting the water sample into a pressure container;
opening a peristaltic pump to force the water sample to permeate the filter membrane in a positive pressure mode;
after all water samples are filtered, taking out the filter membrane;
and after the filter membrane is dried, comparing the color of the filter membrane with a colorimetric card, and determining the concentration of the water sample and the type of suspended solids in the water sample.
4. The method for measuring the trace suspended solids in the water of the nuclear power plant as claimed in claim 3, wherein the concentration on the color chart is in the range of 10-1000 μ g/kg.
5. The method as claimed in claim 4, wherein the colorimetric card comprises Fe3O4、Fe2O3·Fe3O4·NiO、Fe2O3H2O color comparison card.
6. The method for measuring the trace suspended solids in water of nuclear power plant according to claim 5, wherein the Fe2O3·Fe3O4Fe in NiO Compound2O3：Fe3O4: the ratio of NiO is 2:1:3 or 1:2:3 or 1:4: 5.
7. The method for measuring the trace suspended solids in the water of the nuclear power plant according to claim 6, wherein the sampling volume of the water sample to be measured is 1L.
8. The method of claim 7, wherein Fe is used as a reference for measuring the amount of suspended trace solids in water from a nuclear power plant3O4R in RGB value of color comparison card= G = B and R ranges from 250-70, corresponding to Fe3O4The concentration range of (A) is 10-1000. mu.g/kg.
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Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3893333A (en) * | 1972-11-15 | 1975-07-08 | Agency Ind Science Techn | Device for automatic determination of suspended solids content in water |
| CN103928068A (en) * | 2013-01-14 | 2014-07-16 | 上海核工程研究设计院 | System and method for quantitatively measuring pressurized water reactor nuclear power plant circuit coolant leakage rate |
-
2021
- 2021-02-07 CN CN202110175867.0A patent/CN112816263A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3893333A (en) * | 1972-11-15 | 1975-07-08 | Agency Ind Science Techn | Device for automatic determination of suspended solids content in water |
| CN103928068A (en) * | 2013-01-14 | 2014-07-16 | 上海核工程研究设计院 | System and method for quantitatively measuring pressurized water reactor nuclear power plant circuit coolant leakage rate |
Non-Patent Citations (1)
| Title |
|---|
| 张领 等: "滤膜比色法测定痕量悬浮固体的应用研究", 《中国核学会2019年学术年会 中国核科学技术进展报告（第六卷）》, pages 1 - 6 * |
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