CN112651595B - Method for formulating emergency action level of post-processing plant - Google Patents
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Abstract
The invention relates to a method for formulating emergency action level of a post-processing plant, which comprises the following steps: step (1), determining field boundary, meteorological data and other field address specific basic data; determining the duration, accident source items and release ways of the post-processing plant accidents, analyzing the post-processing plant accident situations and estimating environmental radiation consequences; and (3) comparing the environmental radiation consequences estimated in the step (2) with each emergency state grade criterion, determining the emergency state grade of the post-treatment plant accident, and obtaining the concentration of different nuclides of each emergency state grade corresponding to each post-treatment plant accident, namely the emergency action level of the post-treatment plant. The method for formulating the emergency action level of the post-processing plant can provide an effective auxiliary means for the operators and emergency commanders of the post-processing plant to correctly judge the emergency state and make emergency response decisions.
Description
Technical Field
The invention belongs to the technical field of safety analysis of nuclear fuel post-processing plants, and relates to a method for formulating emergency action level of a post-processing plant.
Background
Emergency Action Level (EAL) is a predetermined and observable parameter or criterion used to establish, identify and determine an emergency level and to initiate the execution of a corresponding emergency action. The level of Emergency Action (EAL) may be a specific meter reading or observation, a radiation dose or dose rate, a specific contamination level of gaseous, liquid and solid radioactive or chemically harmful substances, an analysis result, a condition for entering a certain operating protocol, etc.
The establishment of an Emergency Action Level (EAL) requires first an identification class classification, then an initial condition and then a specific Emergency Action Level (EAL) to be determined. The initial condition is a predetermined symptom or indication of a type of Emergency Action Level (EAL) that triggers the nuclear power plant to enter a certain emergency state.
The initial conditions and the level of Emergency Action (EAL) are classified in a certain way, called recognition class. The classification purposes may be different and the resulting recognition classes may be different. The initial conditions and Emergency Action Level (EAL) identification class established by the nuclear power plant should be easy to operate and capable of covering all established Emergency Action Levels (EAL). The initial conditions and the Emergency Action Level (EAL) are classified by four identification classes in China:
a type: radiation level or radioactive effluent abnormalities;
and F: fission product barrier degradation;
and H type: hazards and other events that affect nuclear power plant safety;
and S type: and (6) system failure.
Identification class of the aftertreatment plant on the basis of the above four identification classes of the nuclear power plant, identification classes closely related to special facilities of the aftertreatment plant can be added. The other four basic identification classes are the same concept as for nuclear power plants.
Differences in safety features between the aftertreatment plant and the nuclear power plant must lead to differences in the EAL formulation methods. The greatest difference between the two safety features is the distribution difference of dangerous sources, the distribution of nuclear power plants is relatively concentrated, the distribution of post-treatment plants is wide, and the types of the dangerous sources include dangerous chemicals besides radioactive substances.
For class S of nuclear power plants, the major components include loss of power systems, failure of shutdown systems, loss of safety system forecast signals or indications, loss of communication capability, fuel containment, reactor coolant boundary safety degradation, and loss of heat removal capability. For the class S of the post-treatment plant, besides the loss of the power system, the loss of the forecast signal or indication of the safety system and the loss of the communication capability, the more important part is the accidents related to the safety function, such as critical accidents, red oil explosion accidents of the intermediate or high-level waste liquid evaporator, organic phase combustion accidents and the like, which are typical accidents of the post-treatment plant. The three typical accidents EAL can provide effective auxiliary means for the correct judgment of the emergency state and the emergency response decision of the post-processing plant operating personnel and the emergency commander.
Disclosure of Invention
Aiming at the defects in the prior art, the invention provides a method for making the emergency action level of a post-processing plant, which provides an effective auxiliary means for the operators and emergency commanders of the post-processing plant to correctly judge the emergency state and make emergency response decisions.
In order to achieve the above purposes, the invention adopts the technical scheme that:
a method for establishing an emergency action level of an after-treatment plant is provided, and the method comprises the following steps:
step (1), determining field boundaries, meteorological data and other specific basic data of the field;
determining the duration, accident source items and release ways of the post-processing plant accidents, analyzing the post-processing plant accident situations and estimating environmental radiation consequences;
and (3) comparing the environmental radiation consequences estimated in the step (2) with each emergency state grade criterion, determining the emergency state grade of the post-treatment plant accident, and obtaining the concentration of different nuclides of each emergency state grade corresponding to each post-treatment plant accident, namely the emergency action level of the post-treatment plant.
Further, the post-treatment plant accidents comprise critical accidents of a hot chamber, red oil explosion accidents of a middle-level or high-level discharge waste liquid evaporator and organic phase combustion accidents.
Further, the post-processing plant accident scenario analysis is performed using InteRAS consequence evaluation software.
Further, the scenario analysis of the critical accident of the hot room specifically includes the following steps:
a. acquiring the reading of a gamma dose rate alarm;
b. estimating the critical fission times;
c. estimating a critical fission product;
d. estimating a source item;
e. calculating diffusion;
f. and estimating the environmental radiation effect.
Further, the scenario analysis of the critical accident of the hot chamber further comprises the following steps: the critical prompt dose is estimated after the critical fission number is estimated.
Further, the scene analysis of the red oil explosion accident of the middle-level or high-level discharge waste liquid evaporator specifically comprises the following steps:
a. estimating the yield of the red oil;
b. estimating the effect of explosion;
c. judging whether the evaporator is damaged or not, and if not, ending scene analysis; if the evaporator is damaged, judging whether the filter is damaged;
d. if the filter is not damaged, performing direct source term estimation; if the filter is damaged, estimating the radioactivity released to the equipment room, and then estimating a direct source item;
e. and estimating the environmental radiation effect.
Further, the organic phase combustion accident is a co-decontamination organic phase solvent fire accident.
Further, the scene analysis of the fire accident of the co-decontamination organic phase solvent specifically comprises the following steps:
a. acquiring technological parameters of a co-decontamination organic phase solvent fire accident;
b. estimating a leakage condition;
c. calculating combustion;
d. estimating path weakening silver;
e. calculating a source item;
f. and judging whether the co-decontamination organic phase solvent is burnt out, and if so, estimating the environmental radiation consequence.
Further, the scene analysis of the fire accident of the co-decontamination organic phase solvent further comprises the following steps: and if the co-decontamination organic phase solvent is not burnt out, feeding back the residual oxygen content at the current moment to the step c.
Further, the nuclide classes include inert gases, iodine, aerosols.
The beneficial technical effects of the invention are as follows: according to the safety characteristics of the post-treatment plant, the invention firstly determines the identification class closely related to the special facilities of the post-treatment plant, provides a method for making the emergency action level of three typical accidents of the post-treatment plant, such as critical accidents, medium-level or high-level discharge waste liquid evaporator red oil explosion accidents, organic phase combustion accidents and the like, and provides an effective auxiliary means for the operators and emergency commanders of the post-treatment plant to correctly judge the emergency state and make emergency response decisions.
Drawings
FIG. 1 is a step diagram of a method for establishing emergency action levels of an aftertreatment plant according to embodiment 1 of the invention.
Fig. 2 is a step diagram of scenario analysis of a critical accident of a hot chamber according to embodiment 2 of the present invention.
Fig. 3 is a step diagram of a scene analysis of a red oil explosion accident of the middle-level or high-level waste liquid evaporator provided in embodiment 3 of the present invention.
Fig. 4 is a step diagram of the scene analysis of the fire accident of the co-decontamination organic phase solvent provided in embodiment 4 of the present invention.
Detailed Description
The following describes embodiments of the present invention in further detail with reference to the accompanying drawings.
Example 1
As shown in FIG. 1, the present embodiment provides a method for establishing emergency action level of an aftertreatment plant, the method comprising the following steps:
determining field-address-specific basic data such as field boundaries, meteorological data and the like;
determining the duration, accident source items and release ways of the post-processing plant accidents, analyzing the post-processing plant accident situation by using InteRAS consequence evaluation software, and estimating environmental radiation consequences; the post-treatment plant accidents comprise critical accidents of a hot chamber, red oil explosion accidents of a middle-level or high-level discharge waste liquid evaporator and organic phase combustion accidents.
And (3) comparing the environmental radiation consequences estimated in the step (2) with each emergency state grade criterion, determining the emergency state grade of the post-treatment plant accident, and obtaining the concentration of different nuclides (the nuclide category comprises inert gas, iodine and aerosol) of each emergency state grade corresponding to each post-treatment plant accident, namely the emergency action level of the post-treatment plant.
Example 2
Scenario analysis of critical incidents of a hot cell
In 1953, the nuclear fuel cycle process has 22 nuclear critical accidents in total, and the accident consequences are seriously influenced. Critical accidents may occur due to initiation events such as fissile accumulation, fissile concentration, fissile precipitation, neutron moderation, neutron poison loss, geometric security loss, human error, and the like. Critical accidents of the hot cell, which may occur in different critical systems, are mainly UO2(NO3)2Solution, U3O8Powder, PuO2Powder, Pu (NO)3)4Solution, Pu (C)2O4)2The critical accident may occur in slurry or sediment, and as shown in fig. 2, the scenario analysis of the critical accident in the hot chamber specifically includes the following steps:
a. acquiring the reading of a gamma dose rate alarm;
b. estimating the critical fission times and the critical instantaneous dose;
c. estimating a critical fission product;
d. estimating a source item;
e. calculating diffusion;
f. and estimating the environmental radiation effect.
In the scene analysis, the real-time estimation of the gamma dose rate alarm is mainly reported by NUREG/CR-6504 of the nuclear canal administration (NRC).
Example 3
Scenario analysis of red oil explosion accident of medium-level or high-level waste liquid evaporator
The reaction of TBP-kerosene with hot concentrated nitric acid and uranyl nitrate solutions produces nitrated TBP containing heavy metals and similar mixtures, red oily substances, known as "red oils". Red oil is thermodynamically unstable, accumulates to a certain amount, and at 130 ℃ or higher, it may be decomposed violently by autocatalytic heat to explode.
There have been many red oil explosion accidents historically in the reprocessing industry, such as samfana river plant 1953, hanford plant 1953, oak putting chemical plant 1959, H-canyon plant 1975, uranium trioxide plant canada, ciba chemical association (tombusk-7 plant) 1993, and wentzkel plant in uk, all of which have similar incidents. As shown in fig. 3, the scenario analysis of the red oil explosion accident of the middle-level or high-level waste liquid evaporator specifically includes the following steps:
a. estimating the yield of the red oil;
b. estimating the effect of explosion;
c. judging whether the evaporator is damaged or not, and if not, ending scene analysis; if the evaporator is damaged, judging whether the filter is damaged;
d. if the filter is not damaged, performing direct source term estimation; if the filter is damaged, estimating the radioactivity released to the equipment room, and then estimating a direct source item;
e. and estimating the environmental radiation effect.
Example 4 situational analysis of Co-decontaminated organic phase solvent fire incident
Both the extractant and diluent in the post-processing production are organic solvents and, once the organic solvent leaks and there is again an ignition source, a fire event may occur. The common decontamination organic phase solvent ignition accident is a typical organic phase solvent ignition accident, and has representative significance in research. As shown in fig. 4, the scenario analysis of the fire accident of the co-decontamination organic phase solvent specifically includes the following steps:
a. acquiring technological parameters of a co-decontamination organic phase solvent fire accident;
b. estimating a leakage condition;
c. calculating combustion;
d. estimating path weakening silver;
e. calculating a source item;
f. and c, judging whether the co-decontamination organic phase solvent is burnt out, if so, estimating the environmental radiation effect, and if not, feeding back the residual oxygen content at the current moment to the step c.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The foregoing examples or embodiments are merely illustrative of the present invention, which may be embodied in other specific forms or in other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.
Claims (5)
1. A method for establishing a level of emergency action in an aftertreatment plant, the method comprising the steps of:
step (1), determining field boundary, meteorological data and other field address specific basic data;
determining the duration, accident source items and release ways of the post-processing plant accidents, analyzing the post-processing plant accident situations and estimating environmental radiation consequences;
step (3), comparing the environmental radiation consequences estimated in the step (2) with each emergency state grade criterion, determining the emergency state grade of the post-treatment plant accidents, and obtaining the concentration of different nuclides of each emergency state grade corresponding to each post-treatment plant accident, namely the emergency action level of the post-treatment plant;
wherein, the post-treatment plant accidents comprise critical accidents of a hot chamber, red oil explosion accidents of a middle-level or high-level discharge waste liquid evaporator and organic phase combustion accidents;
the scenario analysis of the critical accident of the hot cell specifically comprises the following steps:
a. acquiring the reading of a gamma dose rate alarm;
b. estimating the critical fission times;
c. estimating a critical fission product;
d. estimating a source item;
e. calculating diffusion;
f. estimating environmental radiation consequences;
the scene analysis of the red oil explosion accident of the middle-level or high-level waste liquid evaporator specifically comprises the following steps:
a. estimating the yield of the red oil;
b. estimating the effect of explosion;
c. judging whether the evaporator is damaged or not, and if not, ending scene analysis; if the evaporator is damaged, judging whether the filter is damaged;
d. if the filter is not damaged, performing direct source term estimation; if the filter is damaged, estimating the radioactivity released to the equipment room, and then estimating a direct source item;
e. estimating the environmental radiation consequence;
the organic phase combustion accident is a co-decontamination organic phase solvent fire accident, and the scene analysis of the co-decontamination organic phase solvent fire accident specifically comprises the following steps:
a. acquiring technological parameters of a co-decontamination organic phase solvent fire accident;
b. estimating a leakage condition;
c. calculating combustion;
d. estimating a path reduction factor;
e. calculating a source item;
f. and judging whether the co-decontamination organic phase solvent is burnt out, and if so, estimating the environmental radiation consequence.
2. A method of developing a level of aftertreatment plant emergency actions according to claim 1 wherein the aftertreatment plant accident scenario analysis is performed using intersas outcome assessment software.
3. A method for establishing a level of emergency action in an aftertreatment plant according to claim 2 wherein the contextual analysis of critical incidents of hot cells further comprises the steps of: the critical prompt dose is estimated after the critical fission number is estimated.
4. A method for establishing a level of emergency action in a post-processing plant according to claim 1, wherein the situational analysis of an accident of a co-decontamination organic solvent fire further comprises the steps of: and if the co-decontamination organic phase solvent is not burnt out, feeding back the residual oxygen content at the current moment to the step c.
5. A method for establishing a level of emergency action in a post-processing plant as claimed in claim 1, wherein the nuclide classes include inert gases, iodine, aerosols.
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