CN112349445B - Temporary storage decay treatment method for high-dose-rate miscellaneous dry wastes of nuclear power station - Google Patents
Temporary storage decay treatment method for high-dose-rate miscellaneous dry wastes of nuclear power station Download PDFInfo
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- CN112349445B CN112349445B CN202011031186.9A CN202011031186A CN112349445B CN 112349445 B CN112349445 B CN 112349445B CN 202011031186 A CN202011031186 A CN 202011031186A CN 112349445 B CN112349445 B CN 112349445B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
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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
- G01T1/02—Dosimeters
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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
- G01T1/167—Measuring radioactive content of objects, e.g. contamination
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
- G21F9/301—Processing by fixation in stable solid media
Abstract
The invention relates to a temporary storage decay treatment method for high-dose-rate miscellaneous dry wastes of a nuclear power station, which comprises the following steps of: 1. carrying out nuclide analysis and measurement on the high-dose rate miscellaneous dry waste to determine the species and the initial activity of the radionuclide; 2. calculating the decay time t required by the surface dose rate of the high dose rate miscellaneous dry waste to reach 2mSv/h according to the radionuclide species and the initial activity determined in the step 1 1 (ii) a 3. Loading the high-dosage-rate miscellaneous dry waste into a barrel for temporary storage, wherein the temporary storage time is more than decay time t 1 (ii) a 4. After the temporary storage time is reached, the barrel in the step 3 is taken back, and the surface dosage rate of the barrel is measured; 5. and (5) according to the measurement result of the step 4, if the surface dosage rate of the barrel exceeds 2mSv/h, returning to the step 1, and circulating the operation until the surface dosage rate of the barrel is less than 2mSv/h. The processing method is standardized, strong in operability and high in safety margin.
Description
Technical Field
The invention belongs to the technical field of radioactive waste treatment, and particularly relates to a temporary storage decay treatment method for high-dose-rate miscellaneous dry waste of a nuclear power station.
Background
The high-dose-rate miscellaneous dry waste refers to radioactive dry waste with the surface dose rate of more than or equal to 2mSv/h. The general treatment method comprises the following steps: miscellaneous dry wastes with the surface dose rate of more than or equal to 2mSv/h are fixed in a 400L steel barrel or a 2000L cement barrel by using cement, and the capacity of the wastes is increased by 2-2.5 times; and (3) collecting miscellaneous dry wastes with the surface dose rate of less than 2mSv/h, drying, pre-pressing in a 200L steel barrel, super-compacting, grouting and fixing in a 400L steel barrel, and reducing the volume of the wastes by about 4.5 times.
The existing treatment of high-dosage-rate miscellaneous dry wastes of nuclear power stations has the following problems: 1. no standard procedure for high dose rate miscellaneous dry waste treatment was established; 2. the existing treatment method has large radioactive waste capacity increase; 3. the temporary storage time of the high-dose rate miscellaneous dry waste is not quantitatively calculated and analyzed, and needs to be measured periodically, so that manpower, material resources and personnel irradiation dose are increased.
Disclosure of Invention
Based on the above, the invention aims to provide a temporary storage decay treatment method for high-dose-rate miscellaneous dry wastes of a nuclear power station, which is standardized, strong in operability and high in safety margin.
In order to achieve the above purpose, the invention provides the following technical scheme:
a temporary storage decay treatment method for high-dose-rate miscellaneous dry wastes of a nuclear power station comprises the following steps:
1. carrying out nuclide analysis and measurement on the high-dose rate miscellaneous dry waste to determine the species and the initial activity of the radionuclide;
2. according to step 1Determining the species and initial activity of the radionuclide, and calculating the decay time t required by the surface dose rate of the high dose rate miscellaneous dry waste to reach 2mSv/h through decay of the t time 1 ；
3. Loading the high-dosage-rate miscellaneous dry waste into a barrel for temporary storage, wherein the temporary storage time is more than decay time t 1 ；
4. After the temporary storage time is reached, the barrel in the step 3 is taken back, and the surface dosage rate of the barrel is measured;
5. and (4) returning to the step 1 if the barrel surface dosage rate exceeds 2mSv/h according to the measurement result of the step 4, and circulating the operation until the barrel surface dosage rate is less than 2mSv/h.
Preferably, the high dose rate miscellaneous dry waste in step 1 is obtained by: collecting radioactive miscellaneous dry waste of a nuclear power station, and measuring the surface dose rate D' of the radioactive miscellaneous dry waste; according to the measurement result, screening high-dose-rate radioactive miscellaneous dry wastes with the surface dose rate exceeding 2mSv/h, and drying, prepressing, overpressure and grouting fixation of low-dose-rate miscellaneous dry wastes with the surface dose rate less than 2mSv/h.
Preferably, the high dose rate miscellaneous dry waste of step 1 comprises high dose rate miscellaneous dry waste that is easy to mix and high dose rate miscellaneous dry waste that is not easy to mix.
Preferably, the high-dosage-rate miscellaneous dry waste easy to mix uniformly is subjected to nuclide analysis by a sampling analysis method; the high dose rate miscellaneous dry waste which is not easy to mix evenly is subjected to nuclide analysis by using a portable gamma spectrometer.
Preferably, the high dose rate miscellaneous dry waste that is easy to mix uniformly comprises baked pit sludge.
Preferably, the decay time t in step 2 1 Is calculated by the following method:
a. calculating dose rate D at 1m by using air kerma rate constant according to the radionuclide species and initial activity determined in step 1 1 ；
b. Calculating the surface dose rate D 0 ；
c. Tong (Chinese character of 'tong')The measured surface dose rate D' and the calculated surface dose rate D 0 Determining a coefficient k;
d. calculating the dose rate D at 1m at time t through decay of time t 1t ；
f. Calculating the surface dose rate D at time t through decay of time t 0t ；
g. Calculating the actual surface dose rate D at the time t according to the coefficient k t ：D t ＝D 0t *k；
h. Calculating the surface dose rate D of the high dose rate miscellaneous dry waste t Decay time t required for =2mSv/h 1 Then the actual decay time is greater than t 1 The surface dose rate of the high dose rate miscellaneous dry waste is less than 2mSv/h.
Preferably, step 3 specifically comprises the following steps: the high-dose-rate miscellaneous dry waste is filled into a 200L steel barrel, the 200L steel barrel is placed into a shielding container and then is transported to a temporary storage point, the 200L steel barrel is taken out and is placed into a shielding chamber or a shielding compartment for temporary storage, and the temporary storage time is longer than the decay time t 1 。
Preferably, step 4 specifically includes the following steps: and after the temporary storage time is reached, the 200L steel barrel is taken back, and the surface dosage rate of the barrel is measured by a gamma dosage rate meter.
Preferably, the step 5 specifically includes the following steps: and (4) according to the measurement result of the step 4, if the dosage rate of the surface of the barrel exceeds 2mSv/h, returning to the step 1, and circulating the operation until the dosage rate of the surface of the barrel is less than 2mSv/h, and if the dosage rate of the surface of the barrel is less than 2mSv/h, drying, prepressing, overpressure and grouting the miscellaneous dry waste in the barrel for fixing.
Preferably, the surface dose rate is measured by a gamma dose meter, the distance of the measurement point from the object item being 0.01m.
The invention has the beneficial technical effects that:
1. the invention establishes a standard process for high-dosage rate miscellaneous dry waste treatment.
2. The invention realizes the aim of minimizing radioactive waste, reduces the waste disposal cost and lightens the influence of the waste on the environment.
3. The invention determines the temporary storage decay time through quantitative calculation and analysis, improves the working efficiency and reduces the irradiated dose and the irradiated risk of personnel.
4. The radionuclide of the invention adopts measured values, thus improving the data accuracy and ensuring the verifiability of the measurement result.
Drawings
FIG. 1 is a flow chart of a temporary decay treatment method for high dose rate miscellaneous dry waste in accordance with the present invention.
Detailed Description
The invention provides a temporary storage decay treatment method for high-dose-rate miscellaneous dry wastes of a nuclear power station, which comprises the following steps of:
1. collecting radioactive miscellaneous item dry waste of a nuclear power station, measuring the surface dose rate of the radioactive miscellaneous item dry waste by using a gamma dose rate meter, wherein the distance between a measuring point and an object item is 0.01m and is marked as D'; screening high-dose-rate radioactive miscellaneous dry wastes with the surface dose rate exceeding 2mSv/h according to the measurement result; and (3) filling the low-dose-rate miscellaneous dry waste with the surface dose rate of less than 2mSv/h into a 200L steel barrel for drying, pre-compacting in the barrel, super-compacting with the barrel, and filling 2-4 overpressure cakes into a 400L steel barrel for grouting and fixing.
2. The high-dosage-rate miscellaneous dry wastes screened in the step 1 comprise high-dosage-rate miscellaneous dry wastes (dried pit sludge) which are easy to be uniformly mixed and high-dosage-rate miscellaneous dry wastes which are difficult to be uniformly mixed; and (2) performing nuclide analysis and measurement on the high-dose-rate miscellaneous dry wastes screened in the step (1) to determine the species and the initial activity of the radionuclide, wherein the high-dose-rate miscellaneous dry wastes (dried pit sludge) which are easy to be uniformly mixed are subjected to nuclide analysis by adopting a sampling analysis method, and the high-dose-rate miscellaneous dry wastes which are difficult to be uniformly mixed are subjected to nuclide analysis by using a portable gamma spectrometer.
3. Calculating the decay time t required by the surface dose rate of the high dose rate miscellaneous dry waste to reach 2mSv/h according to the radionuclide species and the initial activity determined in the step 2 and the decay time t 1 The method comprises the following steps:
a. utilizing air kerma based on the radionuclide species and initial activity determined in step 2Rate constant calculation 1 meter dose rate D 1 The calculation formula is as follows:
b. calculating the surface dose rate D 0 The calculation formula is as follows:
D 0 ＝D 1 *L 1 2 /L 0 2 ②
c. comparing D' with D 0 The value, determining the coefficient k, the calculation formula is as follows:
k＝D′/D 0 ③
d. calculating the activity A of the radionuclide i by decay over time t it The calculation formula is as follows:
A it ＝A i0 e -λi.t ④
e. calculate dose rate D at 1m at time t according to equation (1) 1t Wherein Ai0 is replaced by A it ；
f. Calculating the surface dose rate D at time t according to equation (2) 0t ；
g. Calculating the actual surface dose rate D at the time t according to the coefficient k t ：D t ＝D 0t *k；
h. Calculating the surface dose rate D of the high dose rate miscellaneous dry waste t Decay time t required for =2mSv/h 1 Then the actual decay time is greater than t 1 The surface dose rate of the high dose rate miscellaneous dry waste is less than 2mSv/h.
In the formula:
Γ i : the air kerma constant of the i-th radionuclide in unit of 10 -3 Gy.m 2 .GBq -1 .h -1 )；
A i0 : the initial activity of the i radionuclide in (GBq);
l: the distance between the measuring point and the surface of the object is 1m;
n: the number of radionuclide species present in the material, dimensionless.
D 0 : calculated surface dose rate, unit (10) -3 Gy.h -1 )；
D 1 : dose rate, unit (10) at 1m calculated -3 Gy.h -1 )；
L 0 : measuring point distance of surface dose rate, which is 0.01m;
L 1 : measuring point distance at the dose rate of 1m, and taking the value as 1m;
d': measured surface dose rate, unit (10) -3 Gy.h -1 )；
A i0 : the initial activity of the i radionuclide in (GBq);
A it : the activity of the i radionuclide at time t, in (GBq);
λ i : the decay constant of the ith radionuclide;
t: the actual decay time;
t 1 : the decay time is calculated.
4. The method comprises the steps of loading high-dose-rate miscellaneous dry wastes into a 200L steel barrel, placing the 200L steel barrel into a shielding container, then transporting to a temporary storage point, taking out the 200L steel barrel, placing the 200L steel barrel into a shielding chamber or a shielding compartment for temporary storage, wherein the temporary storage time is longer than decay time t 1 。
5. And after the temporary storage time is reached, the 200L steel barrel is taken back, the surface dose rate of the barrel is measured by a gamma dose rate meter, and the distance between the measuring point and the object item is 0.01m.
6. And (5) according to the measurement result of the step (5), if the dosage rate of the surface of the barrel exceeds 2mSv/h, returning to the step (3), circularly operating until the dosage rate of the surface of the barrel is less than 2mSv/h, if the dosage rate of the surface of the barrel is less than 2mSv/h, loading the low-dosage rate miscellaneous dry waste in the barrel into a 200L steel barrel for drying, pre-compacting in the barrel, super-compacting in a continuous barrel, and grouting and fixing 2-4 overpressure cakes in a 400L steel barrel.
The above-mentioned embodiments only express several embodiments of the present invention, and the description thereof is more specific and detailed, but not construed as limiting the scope of the present invention. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the inventive concept, which falls within the scope of the present invention. Therefore, the protection scope of the present patent shall be subject to the appended claims.
Claims (8)
1. A temporary storage decay treatment method for high-dose-rate miscellaneous dry wastes of a nuclear power plant is characterized by comprising the following steps:
step 1, carrying out nuclide analysis and measurement on the high-dosage rate miscellaneous dry waste to determine the species and the initial activity of the radionuclide;
step 2, calculating the decay time t required by the surface dose rate of the high dose rate miscellaneous dry waste to reach 2mSv/h according to the radionuclide species and the initial activity determined in the step 1 and the decay time t 1 ；
Step 3, filling the high-dosage-rate miscellaneous dry wastes into a barrel for temporary storage, wherein the temporary storage time is longer than the decay time t 1 ；
Step 4, after the temporary storage time is reached, the barrel in the step 3 is taken back, and the surface dosage rate of the barrel is measured;
step 5, according to the measurement result in the step 4, if the surface dosage rate of the barrel exceeds 2mSv/h, returning to the step 1, and circularly operating until the surface dosage rate of the barrel is less than 2mSv/h;
the high dose rate miscellaneous dry waste in step 1 is obtained by the following process: collecting radioactive miscellaneous dry wastes of a nuclear power station, and measuring the surface dose rate D' of the radioactive miscellaneous dry wastes; screening high-dose-rate radioactive miscellaneous dry wastes with the surface dose rate exceeding 2mSv/h according to the measurement result, and drying, prepressing, overpressure and grouting fixation of low-dose-rate miscellaneous dry wastes with the surface dose rate less than 2mSv/h;
the decay time t in step 2 1 Is calculated by the following method:
a. calculating dose rate D at 1m by using air kerma rate constant according to the radionuclide species and initial activity determined in step 1 1 ；
b. Calculating surface dose rateD 0 ；
c. By means of the measured surface dose rate D' and the calculated surface dose rate D 0 Determining a coefficient k;
d. calculating the dose rate D at 1m at time t through decay of time t 1t ；
f. Calculating the surface dose rate D at time t through decay of time t 0t ；
g. Calculating the actual surface dose rate D at the time t according to the coefficient k t ：D t ＝D 0t *k；
h. Calculating the surface dose rate D of the high dose rate miscellaneous dry waste t Decay time t required for =2mSv/h 1 Then the actual decay time is greater than t 1 The surface dose rate of the high dose rate miscellaneous dry waste is less than 2mSv/h.
2. The temporary decay treatment method for nuclear power plant high dose rate miscellaneous dry wastes according to claim 1, wherein the high dose rate miscellaneous dry wastes in step 1 comprise high dose rate miscellaneous dry wastes which are easy to mix uniformly and high dose rate miscellaneous dry wastes which are not easy to mix uniformly.
3. The temporary decay treatment method for the nuclear power plant high dose rate miscellaneous dry wastes according to claim 2, wherein the high dose rate miscellaneous dry wastes which are easy to be uniformly mixed are subjected to nuclide analysis by a sampling analysis method; the high dose rate miscellaneous dry waste which is not easy to mix evenly is subjected to nuclide analysis by using a portable gamma spectrometer.
4. The temporary decay treatment process for nuclear power plant high dose rate miscellaneous dry waste as claimed in claim 2, wherein the easy to mix high dose rate miscellaneous dry waste comprises baked pit sludge.
5. The temporary decay treatment method for high dose rate miscellaneous dry waste in nuclear power plants as claimed in claim 1, wherein step 3 specifically comprises the following steps: adding the high agentThe method comprises the steps of loading rate miscellaneous dry wastes into a 200L steel drum, placing the 200L steel drum into a shielding container, then transporting to a temporary storage point, taking out the 200L steel drum, placing the 200L steel drum into a shielding chamber or a shielding compartment for temporary storage, wherein the temporary storage time is longer than decay time t 1 。
6. The temporary decay treatment method for high dose rate miscellaneous dry waste in nuclear power plants as claimed in claim 5, wherein step 4 comprises the following steps: and after the temporary storage time is reached, the 200L steel barrel is taken back, and the surface dosage rate of the barrel is measured by a gamma dosage rate meter.
7. The temporary decay treatment method for high dose rate miscellaneous dry waste in nuclear power plants as claimed in claim 1, wherein said step 5 comprises the following steps: and (4) according to the measurement result of the step 4, if the dosage rate of the surface of the barrel exceeds 2mSv/h, returning to the step 1, and circulating the operation until the dosage rate of the surface of the barrel is less than 2mSv/h, and if the dosage rate of the surface of the barrel is less than 2mSv/h, drying, prepressing, overpressure and grouting the miscellaneous dry waste in the barrel for fixing.
8. The temporary decay treatment method for high dose rate miscellaneous dry wastes of nuclear power plants according to any one of claims 1 to 7, wherein the surface dose rate is measured by a gamma dose meter, and the distance between the measuring point and the object item is 0.01m.
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