CN112489830B - Method for cleaning and controlling waste resin of blow-down system of steam generator of nuclear power plant - Google Patents
Method for cleaning and controlling waste resin of blow-down system of steam generator of nuclear power plant Download PDFInfo
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- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention relates to the technical field of radioactive waste management, and particularly discloses a method for cleaning and controlling waste resin of a nuclear power plant steam generator sewage discharge system, which comprises the following steps: step 1: source item investigation; step 2: judging whether the radioactivity is abnormal or not; and step 3: collecting assessment directions separately; and 4, step 4: sampling and measuring gamma nuclide; and 5: calculating the number of statistical samples; step 6: judging whether the number of samples meets the requirement or not; and 7: calculating the sum of the activity and concentration of the gamma of the sample, and judging whether the sum is less than or equal to 0.01Bq/g; and step 8: 3 H、 14 C、 90 sr measurement; and step 9: performing solution control evaluation; step 10: controlling; step 11: no control is performed. The method of the invention realizes the aim of minimizing radioactive waste, reduces the cost of waste disposal and lightens the influence of waste on the environment.
Description
Technical Field
The invention belongs to the technical field of radioactive waste management, and particularly relates to a method for cleaning and controlling waste resin of a nuclear power plant steam generator sewage discharge system.
Background
The Chinese radiation protection institute Guo Xiliang provides a basic process for cleaning and controlling slightly radioactive contaminated materials (Guo Xiliang and other works, cleaning and controlling slightly radioactive contaminated materials in nuclear power plants, and radiation protection >2014, volume 34, phase 2), which comprises the steps of source item analysis of contaminated materials, radiation level detection content design, radiation level measurement, cleaning and controlling application report, submission of inspection tube part door evaluation, implementation and controlling implementation and the like, and is shown in fig. 1.
The nuclear and radiation safety center Wang Ping of the environmental protection department proposes an analysis program for preparing materials to be controlled (Wang Ping et al, clean control of radioactive materials, volume 14, 2 nd of 2015 < nuclear safety >), which comprises the steps of material preparation, preliminary classification, dose rate screening measurement/surface contamination measurement/sampling nuclide analysis, clean control/radioactive waste and the like, as shown in fig. 2.
The two cleaning and control methods are relatively wide processes, are not strong in pertinence, do not make a specific process according to material characteristics, namely waste resin of a nuclear power plant steam generator blowdown system, do not form a closed loop in the processes, and do not have specific data judgment standards in the processes; and a standardized flow is not formed, and the method cannot be used for field implementation.
Disclosure of Invention
The invention aims to provide a method for cleaning and controlling waste resin of a blow-down system of a steam generator of a nuclear power plant, which can standardize a cleaning and controlling process, improve operability and improve safety margin.
The technical scheme of the invention is as follows:
a method for cleaning and controlling waste resin of a nuclear power plant steam generator blowdown system comprises the following steps:
step 1: source item investigation;
the method comprises the steps of knowing the leakage condition of a steam generator and the radioactivity condition of blowdown water by investigating the running condition and the radioactivity level of a secondary loop of each monitoring channel of the nuclear power plant, and verifying the integrity of a U-shaped tube barrier of the steam generator by monitoring the radiation conditions of waste resin replacement and barreling of a blowdown system of the steam generator;
step 2: judging whether the radioactivity is abnormal or not;
if the waste resin generated by the steam generator sewage system is not polluted by radioactivity or only slightly polluted by radioactivity, the radioactivity is not abnormal, and the step 4 is skipped;
if the monitoring channel gives an alarm or the total activity of the discharged water gamma of the steam generator exceeds the detection limit or the radiation monitoring exceeds the background level, the radioactivity is abnormal, and the steam generator is required to be separately collected and evaluated to go to step 3;
and step 3: collecting assessment directions separately;
and 4, step 4: sampling and measuring gamma nuclide;
gamma nuclide analysis of waste resin samples of steam generator blowdown system is carried out by high purity germanium gamma spectrometer according to the specific activity measurement requirement of GBT17947-2008,4.3, the radioactivity measurement of solid matter to be recycled, reused or disposed of as non-radioactive waste, each sample is used for measuring gamma nuclide once, and the species of the measured nuclide comprises 58 Co、 60 Co、 54 Mn、 110m Ag、 124 Sb、 125 Sb、 131 I、 133 I、 59 Fe、 51 Cr、 95 Zr、 95 Nb、 134 Cs、 137 Cs；
And 5: calculating the number of statistical samples;
and 6: judging whether the number of samples meets the requirement or not;
if the number of the sampled samples is less than the required number, increasing the number of the samples, and recalculating until the requirements are met;
and 7: calculating the sum of the activity and concentration of the gamma of the sample, and judging whether the sum is less than or equal to 0.01Bq/g;
respectively counting the radioactivity concentration of the ith gamma artificial radionuclide in each batch of samples, and recording as C i If the activity concentration of the nuclide is less than the detection limit, counting the activity concentration according to the detection limit, and then calculating the sum of the gamma activity concentrations of each batch of samples;
if the sum of the gamma activity concentrations of the samples>0.01Bq/g，The batch of steam generator blowdown system resin waste increases 3 H、 14 C、 90 Sr measurement, go to step 8;
if the sum of the gamma activity and the concentration of the sample is less than or equal to 0.01Bq/g, directly performing solution control evaluation on the waste resin of the steam generator sewage system, and skipping to the step 9;
and 8: 3 H、 14 C、 90 sr measurement;
taking the number of samples measured by each nuclide to be more than 3, and calculating according to the maximum value of the activity concentration measured by each nuclide;
and step 9: performing solution control evaluation;
the concentration value of the artificial radionuclide without being managed is determined in GB27742-2011, and for a material containing a mixture of multiple artificial radionuclides, the sum of the ratios of the activity concentrations of the various artificial radionuclides to the respective concentration values without being managed is required to be less than or equal to 1, namely:
in the formula:
C i the activity concentration Bq/g of the ith artificial radionuclide in the material, which is measured in the step 4 and the step 8;
C oi the tube-free concentration of the ith artificial radionuclide refers to the activity concentration of the radionuclide in the material (GB 27742-2011) which can be free from radiation protection supervision, bq/g by specific numerical values;
n, the number of classes of artificial radionuclides present in the material, determined in steps 4 and 8, is dimensionless;
the activity concentration of the ith artificial radionuclide is less than the detection limit, and the activity concentration is counted according to the detection limit;
when the activity concentration of the main radioactive contamination nuclide of the sample meets the formula (3), the waste resin of the blowdown system of the steam generator can be subjected to solution control, and the step 10 is carried out;
when the activity concentration of the main radioactive contamination nuclide of the sample does not meet the formula (3), the waste resin of the blowdown system of the steam generator is not subjected to solution control, and the step 11 is skipped;
step 10: controlling;
step 11: no control is performed.
Step 1 specifically includes the following survey:
1.1 investigating the running conditions of a gamma activity monitoring channel of the sewage discharged by the steam generator, a beta activity monitoring channel of the condenser and an N16 monitoring channel for detecting the leakage of one loop to the second loop;
1.2, a chemical analyst periodically samples and analyzes the sewage discharged by the steam generator during the operation period, measures the total activity and knows the radioactivity level of the sewage discharged by the steam generator;
1.3 survey radiation monitoring of steam generator blowdown system waste resin replacement and barreling.
The specific judgment criteria of step 2 are as follows:
2.1 no alarm occurs in a gamma activity monitoring channel of the sewage discharged by the steam generator, a beta activity monitoring channel of the condenser and an N16 monitoring channel for detecting the leakage of one loop to the second loop;
2.2 the total activity of the discharged sewage gamma of the steam generator does not exceed the detection limit;
2.3 waste resin replacement and radiation monitoring of the barrel are background levels.
And 3, under the condition of radioactive abnormality, independently collecting waste resin generated by a steam generator sewage system, carrying out nuclide analysis and calculation evaluation, if the temporary storage decay can reach a level below a cleaning solution control level, independently storing the decay, then carrying out a cleaning solution control flow, and otherwise, carrying to a solid waste treatment system for curing treatment.
In step 4, a layered random sampling method is adopted for sampling the resin of the blowdown system of the steam generator, waste barrels on the same layer are waste barrels in the same batch, and the waste barrels are in the same layer during storage, so that the sampling representativeness of the resin of the blowdown system of the steam generator in different running batches is ensured; and random sampling method is adopted for the waste barrels in the same batch, so that the sampling representativeness of the same batch is ensured.
In step 8, of resin sample 3 H、 14 C, analysis:
waste resin sample is filled into quartz tube, connected to oxidizing combustion device, heated combustion chamber to completely oxidize the sample, and then connected with bubblers filled with water and NaOH alkali solution for respectively trapping 3 H and total 14 C；
Taking water sample, adding scintillation liquid, and performing light-shielding liquid flash analysis 3 H, referring to GB _ T12375 analysis method of tritium in water in the concrete method;
taking NaOH alkaline solution, accurately transferring 8ml of sample absorbed by NaOH solution to the sample by using a special liquid transfer device 14 C measuring flask, adding 12ml scintillation liquid 14 C in a measuring bottle, shaking up to obtain 14 C, sampling; is prepared by 14 C, standing the sample in a low background liquid scintillation spectrometer measuring disc for one hour in a dark place, and performing light-proof liquid scintillation analysis 14 C, specifically calculated according to formula (2):
C i the concentration of the radioactivity of the nuclide in the sample to be tested, defines 14 C is the 16 th measured nuclide, when i =16,bq/g;
ns, the counting rate of the sample to be measured read from the instrument, cps;
nb, background sample count rate, cps read from the instrument;
ρ, sample density, g/ml;
v, sample volume matched with scintillation liquid, 8ml;
E， 14 c, directly reading from a nameplate of the low-background liquid scintillation spectrometer by using the counting efficiency and the inherent properties of the instrument;
of the resin samples 90 Analysis of Sr: waste resin samples were placed in a three-necked flask and then H was added 2 O 2 Under the action of catalyst, the waste resin is completely dissolved to prepare waste resin digestion liquid; in waste resin digestion liquid 90 Analysis of Sr reference Standard-radiochemical analysis of strontium-90 in WaterThe method comprises the following steps: the extraction chromatography of di- (2-ethylhexyl) phosphoric acid is carried out in GB/T6766 and the radiochemical analysis method of strontium-90 in water-fuming nitric acid precipitation method GB 6764.
In step 5, the number of samples should have a sufficient statistical basis to achieve a 95% confidence level of the results obtained with the minimum number of samples, according to the rules of GBT17947-2000 measurement of the activity of solid matter to be recycled, reused or disposed of as non-radioactive waste, clause 4.4, and the number of samples N that meet the statistical requirements can be calculated as follows:
wherein S is the standard deviation of the measured values of the gamma nuclide of the N samples,
is the average of the gamma nuclide measurements for the N samples.
In step 10, reuse of waste resin of a steam generator blowdown system is considered; secondly, the waste is recycled and reused by related units, the recycling is clear in a contract way, and all units receiving the steam generator drainage system resin have to meet the national relevant regulations and standards for treating and disposing the waste; finally, according to the common industrial waste treatment and disposal, the steam generator pollution discharge system resin without reuse value is received and disposed by manufacturers with corresponding waste treatment qualification.
In step 11, collecting waste resin without solution control separately, analyzing nuclide, calculating and evaluating, if the evaluation can reach below the clean solution control level within the expected age, storing and decaying separately, and applying for solution control later; if it is estimated that the cleaning solution level is not reached below the expected cleaning solution level within the expected period of time, the solid waste treatment system is transported to a curing treatment.
The invention has the following remarkable effects:
(1) The invention sets up a source item investigation scheme, improves the efficiency, and can know whether the waste resin of the steam generator sewage system is polluted by radioactivity from the source through necessary source item investigation.
(2) The invention sets a sampling scheme, improves the efficiency and ensures that the waste resin sampling of the steam generator sewage system is representative.
(3) The nuclide measuring method is formulated, so that the measuring precision and accuracy are improved, and the verifiability of the measuring result is ensured.
(4) The method of the invention realizes the aim of minimizing radioactive waste, reduces the cost of waste disposal and lightens the influence of waste on the environment.
(5) The invention establishes a waste resin cleaning and control standard process of the steam generator sewage system, and other nuclear power plants can apply for resin cleaning and control of the steam generator sewage system by referring to the process.
Drawings
FIG. 1 is a flow chart of the cleaning and control-releasing management of radioactive slightly-polluted materials;
FIG. 2 is a schematic diagram of an analysis process for preparing a controlled material;
FIG. 3 is a flow chart illustrating a resin cleaning control for the blowdown system of the steam generator of the present invention;
FIG. 4 is a schematic drawing of resin layer sampling.
Detailed Description
The invention is described in further detail below with reference to the figures and the embodiments.
Fig. 3 shows a method for cleaning and controlling waste resin in a blowdown system of a steam generator of a nuclear power plant, which comprises the following steps:
step 1: source item survey
Through the operational aspect and the two return circuits radioactivity level of surveying each monitoring way of nuclear power plant, know steam generator and leak the condition and blowdown water radioactivity condition, through the radiation monitoring condition that the useless resin of steam generator drainage was changed, barrelling, verify the integrality of steam generator U type pipe protective screen, specifically include following investigation content:
1.1 investigating the running conditions of a gamma activity monitoring channel of the sewage discharged by the steam generator, a beta activity monitoring channel of the condenser and an N16 monitoring channel for detecting the leakage of one loop to the second loop;
1.2, a chemical analyzer periodically samples and analyzes the discharged water of the steam generator during the operation period, measures the total activity and knows the radioactivity level of the discharged water of the steam generator;
1.3 investigating the radiation monitoring conditions of waste resin replacement and barreling of a steam generator sewage system;
step 2: determine whether the radioactivity is abnormal or not
If the waste resin generated by the steam generator sewage system is not polluted by radioactivity or only slightly polluted by radioactivity, the radioactivity is not abnormal, the operation jumps to the step 4, and the specific judgment standard is as follows:
2.1 no alarm occurs in a gamma activity monitoring channel of the discharged water of the steam generator, a beta activity monitoring channel of the condenser and an N16 monitoring channel for detecting the leakage of one loop to the second loop;
2.2 the total activity of the discharged water gamma of the steam generator does not exceed the detection limit;
2.3 the radiation monitoring condition of waste resin replacement and barreling is a background level;
if the alarm is given out on the monitoring channel or the total gamma activity of the discharged water of the steam generator exceeds the detection limit or the radiation monitoring exceeds the background level, the radioactivity is abnormal, and the direction needs to be separately collected and evaluated, and the step 3 is carried out;
and step 3: separate collection of assessment leads
Under the condition of radioactive abnormality, independently collecting waste resin generated by a steam generator sewage system, and carrying out nuclide analysis and calculation evaluation, wherein if the temporary storage decay can reach a level below a clean solution level, independently storing the decay, then carrying out a clean solution flow, and otherwise, carrying to a solid waste treatment system for curing treatment;
and 4, step 4: sampling measurement of gamma nuclide
As shown in fig. 4, the sampling of the steam generator waste system resin adopts a layered random sampling method, and waste barrels on the same layer are waste barrels in the same batch, and the waste barrels are in the same layer when being stored, so that the sampling representativeness of the steam generator waste system resin in different operation batches is ensured; the waste barrels in the same batch adopt a random sampling method, so that the sampling representativeness of the same batch is ensured;
according to the specific activity measurement requirement of 4.3 in the radioactivity measurement of solid substances to be recycled, reused or disposed of as non-radioactive waste (GBT 17947-2008), gamma nuclide analysis of waste resin samples of a steam generator blowdown system is carried out by using a high-purity germanium gamma spectrometer, wherein each sample is used for measuring gamma nuclide once, and the measured nuclide types comprise 58 Co、 60 Co、 54 Mn、 110m Ag、 124 Sb、 125 Sb、 131 I、 133 I、 59 Fe、 51 Cr、 95 Zr、 95 Nb、 134 Cs、 137 Cs；
And 5: calculating the number of statistical samples
According to the provisions of GBT17947-2000 radioactivity measurement of solid materials to be recycled, reused or disposed of as non-radioactive waste, bar 4.4, the number of samples should have a sufficient statistical basis to achieve a 95% confidence level in the results obtained with the minimum number of samples, and the number of samples N meeting the statistical requirements can be calculated by:
wherein S is the standard deviation of the measured values of the gamma nuclide of the N samples,
the average value of the gamma nuclide measured values of the N samples is obtained;
and 6: judging whether the number of samples meets the requirement
Calculating according to the formula (1), if the number of samples of the batch of steam generator blowdown system resin is greater than or equal to N, the samples meet the requirement; if the number of the sampled samples is less than N, increasing the number of the samples, and recalculating until the requirements are met;
and 7: calculating the sum of the activity and concentration of the gamma of the sample, and judging whether the sum is less than or equal to 0.01Bq/g
Respectively counting the radioactivity concentration of the ith gamma artificial radionuclide in each batch of samples, and recording the radioactivity concentration as C i If the activity concentration of the nuclide is less than the detection limit, counting the activity concentration according to the detection limit, and then calculating the sum of the gamma activity concentrations of each batch of samples;
if the sum of the gamma activity concentrations of the samples>0.01Bq/g, the waste resin of the steam generator blow-down system is increased 3 H、 14 C、 90 Sr measurement, go to step 8;
if the sum of the activity and concentration of the gamma of the sample is less than or equal to 0.01Bq/g, the waste resin of the blowdown system of the steam generator can be directly subjected to solution control evaluation, and the step 9 is skipped;
and step 8: 3 H、 14 C、 90 sr measurement
Taking the number of samples measured by each nuclide to be more than 3, and calculating according to the maximum value of the activity concentration measured by each nuclide;
of the resin samples 3 H、 14 C, analysis: waste resin sample is filled into quartz tube, connected to oxidizing combustion device, heated combustion chamber to completely oxidize the sample, and then connected with bubblers filled with water and NaOH alkali solution for respectively trapping 3 H and total 14 C；
Taking water sample, adding scintillation liquid, and performing light-shielding liquid flash analysis 3 H, the concrete method refers to an analysis method of tritium in water (GB _ T12375);
taking NaOH alkaline solution, accurately transferring 8ml of sample absorbed by NaOH solution to a special liquid transfer device 14 C measuring flask, adding 12ml scintillation liquid 14 C in a measuring bottle, shaking up to obtain 14 C, sampling; is prepared by 14 C sample is placed in a low background liquid scintillation spectrometer measuring disc for one hour in a dark place and is analyzed in a dark liquid scintillation way 14 C, specifically calculated according to formula (2):
C i the concentration of the radioactivity of the nuclide in the sample to be tested, defines 14 C is the 16 th measured nuclide, when i =16,bq/g;
ns, the counting rate of the sample to be measured read from the instrument, cps;
nb, background sample count rate, cps read from the instrument;
ρ, sample density, g/ml;
v, sample volume matched with scintillation liquid, 8ml;
E， 14 and C, directly reading from a nameplate of the low-background liquid scintillation spectrometer, wherein the counting efficiency and the inherent properties of the instrument are shown in the specification.
Of the resin samples 90 Analysis of Sr: waste resin samples were placed in a three-necked flask and then H was added 2 O 2 Under the action of catalyst, the waste resin is completely dissolved to prepare waste resin digestion liquid; in waste resin digestion liquid 90 Analysis of Sr refers to standard "method for radiochemical analysis of strontium-90 in water: extraction chromatography of di- (2-ethylhexyl) phosphoric acid (GB/T6766) and radiochemical analysis of strontium-90 in water-fuming nitric acid precipitation (GB 6764).
And step 9: solution control evaluation
The concentration activity of radioactive nuclides in materials which can be free from radiation protection supervision (GB 27742-2011) defines the tube-free concentration value of the artificial radionuclide, and for materials containing a mixture of a plurality of artificial radionuclides, the sum of the ratios of the activity concentrations of the various artificial radionuclides to the respective tube-free concentration values is required to be less than or equal to 1, namely:
in the formula:
C i the activity concentration Bq/g of the ith artificial radionuclide in the material, which is measured in the step 4 and the step 8;
C oi the tube-free concentration of the ith artificial radionuclide, and the specific numerical value of the tube-free concentration refer to the radioactivity of the radionuclide in the material which can be free from radiation protection supervisionConcentration (GB 27742-2011), bq/g;
n, the number of classes of artificial radionuclides present in the material, determined in steps 4 and 8, is dimensionless;
the activity concentration of the ith artificial radionuclide is less than the detection limit, and the activity concentration is counted according to the detection limit;
when the activity concentration of the main radioactive contamination nuclide of the sample meets the formula (3), the waste resin of the blowdown system of the steam generator can be subjected to solution control, and the step 10 is carried out;
when the activity concentration of the main radioactive contamination nuclide of the sample does not meet the formula (3), the waste resin of the blowdown system of the steam generator is not subjected to solution control, and the step 11 is skipped;
step 10: control solution
Firstly, waste resin reuse of a steam generator sewage discharge system is considered, and if the waste resin is reused, the waste resin enters a condensate fine treatment system for in-plant regeneration; secondly, the waste is recycled and reused by related units, the recycling is clear in a contract way, and all units receiving the steam generator drainage system resin have to meet the national relevant regulations and standards for treating and disposing the waste; finally, according to the common industrial waste treatment and disposal, the steam generator pollution discharge system resin without reuse value is received and disposed by manufacturers with corresponding waste treatment qualification.
Step 11: without control
Separately collecting waste resin which is not subjected to solution control, performing nuclide analysis and calculation evaluation, if the evaluation can reach a level below a clean solution control level within an expected age, separately storing for decay, and subsequently applying for solution control; if it is estimated that the cleaning release level cannot be reached below the expected age, the solid waste treatment system is transported to a curing treatment.
Claims (9)
1. A method for cleaning and controlling waste resin of a nuclear power plant steam generator blowdown system is characterized by comprising the following steps: the method comprises the following steps:
step 1: source item investigation;
the method comprises the steps of knowing the leakage condition of a steam generator and the radioactivity condition of blowdown water by investigating the running condition and the radioactivity level of a secondary loop of each monitoring channel of the nuclear power plant, and verifying the integrity of a U-shaped tube barrier of the steam generator by monitoring the radiation conditions of waste resin replacement and barreling of a blowdown system of the steam generator;
step 2: judging whether the radioactivity is abnormal or not;
if the waste resin generated by the steam generator sewage system is not polluted by radioactivity or is only slightly polluted by radioactivity, the radioactivity is abnormal, and the step 4 is skipped;
if the alarm is given out on the monitoring channel or the total gamma activity of the discharged water of the steam generator exceeds the detection limit or the radiation monitoring exceeds the background level, the radioactivity is abnormal, and the direction needs to be separately collected and evaluated, and the step 3 is carried out;
and 3, step 3: collecting assessment directions separately;
and 4, step 4: sampling and measuring gamma nuclide;
gamma nuclide analysis of waste resin samples of steam generator blowdown system is carried out by high purity germanium gamma spectrometer according to the specific activity measurement requirement of GBT17947-2008,4.3, the radioactivity measurement of solid matter to be recycled, reused or disposed of as non-radioactive waste, each sample is used for measuring gamma nuclide once, and the species of the measured nuclide comprises 58 Co、 60 Co、 54 Mn、 110m Ag、 124 Sb、 125 Sb、 131 I、 133 I、 59 Fe、 51 Cr、 95 Zr、 95 Nb、 134 Cs、 137 Cs；
And 5: calculating the number of statistical samples;
step 6: judging whether the number of samples meets the requirement;
if the number of the sampled samples is less than the required number, increasing the sampling number, and recalculating until the requirements are met;
and 7: calculating the sum of the activity and concentration of the gamma of the sample, and judging whether the sum is less than or equal to 0.01Bq/g;
respectively counting the radioactivity concentration of the ith gamma artificial radionuclide in each batch of samples, and recording as C i If the activity concentration of the nuclide is less than the detection limit, counting the activity concentration according to the detection limit, and then calculating the sum of the gamma activity concentrations of each batch of samples;
if the sum of the gamma activity concentrations of the samples>0.01Bq/g, the waste resin of the steam generator blow-down system is increased 3 H、 14 C、 90 Sr measurement, go to step 8;
if the sum of the activity and concentration of the gamma of the sample is less than or equal to 0.01Bq/g, the waste resin of the blowdown system of the steam generator can be directly subjected to solution control evaluation, and the step 9 is skipped;
and 8: 3 H、 14 C、 90 sr measurement;
taking more than 3 samples for each nuclide measurement, and calculating according to the maximum value of the activity concentration measured by each nuclide;
and step 9: performing solution control evaluation;
the free-tube concentration value of the artificial radionuclide is determined in GB27742-2011, and for a material containing a mixture of multiple artificial radionuclides, the sum of the ratios of the activity concentration of each artificial radionuclide to the respective free-tube concentration value is required to be less than or equal to 1, namely:
in the formula:
C i the activity concentration Bq/g of the ith artificial radionuclide in the material, which is measured in the step 4 and the step 8;
C oi the tube-free concentration of the ith artificial radionuclide refers to the activity concentration of the radionuclide in the material (GB 27742-2011) which can be free from radiation protection supervision, bq/g by specific numerical values;
n, the number of the types of the artificial radionuclide in the material, which is measured in the step 4 and the step 8, is dimensionless;
the activity concentration of the ith artificial radionuclide is less than the detection limit, and the activity concentration is counted according to the detection limit;
when the activity concentration of the main radioactive contamination nuclide of the sample meets the formula (3), the waste resin of the blowdown system of the steam generator can be subjected to solution control, and the step 10 is carried out;
when the activity concentration of the main radioactive contamination nuclide of the sample does not meet the formula (3), the waste resin of the blowdown system of the steam generator is not subjected to solution control, and the step 11 is skipped;
step 10: controlling;
step 11: no control is performed;
step 1 specifically includes the following survey content:
1.1 investigating the leakage of the vapor generator blow-off water gamma activity monitoring channel, the condenser beta activity monitoring channel and the detection loop to the second loop 16 N, monitoring the running condition of the road;
1.2, a chemical analyst periodically samples and analyzes the sewage discharged by the steam generator during the operation period, measures the total activity and knows the radioactivity level of the sewage discharged by the steam generator;
1.3 survey radiation monitoring of steam generator blowdown system waste resin replacement and barreling.
2. The method for cleaning and releasing the waste resin in the blowdown system of the steam generator of the nuclear power plant as claimed in claim 1, wherein: the specific judgment criteria of step 2 are as follows:
2.1 no alarm occurs in a gamma activity monitoring channel of the sewage discharged by the steam generator, a beta activity monitoring channel of the condenser and an N16 monitoring channel for detecting the leakage of one loop to the second loop;
2.2 the total activity of the discharged water gamma of the steam generator does not exceed the detection limit;
2.3 waste resin change and barreling radiation monitoring conditions are background levels.
3. The method for cleaning and releasing the waste resin in the blowdown system of the steam generator of the nuclear power plant as claimed in claim 2, wherein: and 3, under the condition of radioactive abnormality, independently collecting waste resin generated by a steam generator sewage system, analyzing and calculating nuclide, if the temporary storage decay can reach the level below the cleaning release level, independently storing the decay, then walking the cleaning release flow, and otherwise, conveying the waste resin to a solid waste treatment system for curing.
4. The method for cleaning and releasing the waste resin in the blowdown system of the steam generator of the nuclear power plant as claimed in claim 3, wherein: in step 4, a layered random sampling method is adopted for sampling the resin of the blowdown system of the steam generator, waste barrels on the same layer are waste barrels in the same batch, and the waste barrels are in the same layer during storage, so that the sampling representativeness of the resin of the blowdown system of the steam generator in different running batches is ensured; and the waste barrels in the same batch adopt a random sampling method, so that the sampling representativeness of the same batch is ensured.
5. The method for cleaning and releasing the waste resin in the blowdown system of the steam generator of the nuclear power plant as claimed in claim 4, wherein: in step 8, of the resin sample 3 H、 14 C, analysis:
waste resin sample is filled into quartz tube, connected to oxidizing combustion device, heated combustion chamber to completely oxidize the sample, and then connected with bubblers filled with water and NaOH alkali solution for respectively trapping 3 H and total 14 C；
Taking a water sample, adding a scintillation fluid, and carrying out light-resistant flash analysis 3 H, referring to a method for analyzing tritium in water GB _ T12375;
taking NaOH alkaline solution, accurately transferring 8ml of sample absorbed by NaOH solution to a special liquid transfer device 14 C measuring flask, adding 12ml scintillation liquid 14 C in a measuring bottle, shaking up to obtain 14 C, sampling; is to be made into 14 C, standing the sample in a low background liquid scintillation spectrometer measuring disc for one hour in a dark place, and performing light-proof liquid scintillation analysis 14 C, specifically calculated according to formula (2):
C i the concentration of radioactivity of a nuclide in a sample to be tested, define 14 C is the 16 th measured nuclide, when i =16,bq/g;
ns, the counting rate of the sample to be measured read from the instrument, cps;
nb, the background sample count rate, cps, read from the instrument;
ρ, sample density, g/ml;
v, sample volume matched with scintillation liquid, 8ml;
E， 14 c, directly reading from a nameplate of the low-background liquid scintillation spectrometer by using the counting efficiency and the inherent properties of the instrument;
of the resin samples 90 Analysis of Sr: waste resin samples were placed in a three-necked flask and then H was added 2 O 2 Under the action of catalyst, the waste resin is completely dissolved to prepare waste resin digestion liquid; in waste resin digestion liquid 90 Analysis of Sr reference standard strontium-90 radiochemical analytical method in water: the extraction chromatography of di- (2-ethylhexyl) phosphoric acid is carried out in GB/T6766 and the radiochemical analysis method of strontium-90 in water-fuming nitric acid precipitation method GB 6764.
6. The method for cleaning and releasing the waste resin in the blowdown system of the steam generator of the nuclear power plant as claimed in claim 5, wherein: in step 5, the number of samples should have a sufficient statistical basis to achieve a 95% confidence level of the results obtained with the minimum number of samples, according to the rules of GBT17947-2000 measurement of the activity of solid matter to be recycled, reused or disposed of as non-radioactive waste, clause 4.4, and the number of samples N that meet the statistical requirements can be calculated as follows:
wherein s is the standard deviation of the measured values of the gamma nuclide of the N samples,
the average of the measured values of the gamma nuclide for the N samples.
7. The method for cleaning and releasing the waste resin in the blowdown system of the steam generator of the nuclear power plant as claimed in claim 6, wherein: step 6, calculating according to the formula (1), and if the number of samples of the batch of steam generator blowdown system resin is larger than or equal to N, sampling to meet the requirement; and if the number of the sampled samples is less than N, increasing the number of the samples, and recalculating until the requirements are met.
8. The method for cleaning and releasing the waste resin in the blowdown system of the steam generator of the nuclear power plant as claimed in claim 7, wherein: in step 10, reuse of waste resin of a steam generator blowdown system is considered; the recycling is reused by related units, the recycling is clear in a contract way, and the treatment and disposal of the waste by all units receiving the steam generator drainage system resin must meet the relevant national regulation and standard; finally, according to the common industrial waste treatment and disposal, the steam generator pollution discharge system resin without reuse value is received and disposed by manufacturers with corresponding waste treatment qualification.
9. The method for cleaning and releasing the waste resin in the blowdown system of the steam generator of the nuclear power plant as claimed in claim 8, wherein: in step 11, collecting waste resin without solution control separately, analyzing nuclide, calculating and evaluating, if the evaluation can reach below the clean solution control level within the expected age, storing and decaying separately, and applying for solution control later; if it is estimated that the cleaning solution level is not reached below the expected cleaning solution level within the expected period of time, the solid waste treatment system is transported to a curing treatment.
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| CN109754888A (en) * | 2019-01-16 | 2019-05-14 | 中国辐射防护研究院 | A method of radioactivity waste oil is handled using spent sorbents in nuclear power station |
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| CN109754888A (en) * | 2019-01-16 | 2019-05-14 | 中国辐射防护研究院 | A method of radioactivity waste oil is handled using spent sorbents in nuclear power station |
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