CN110610008B - Calculation method and device for nuclide release activity - Google Patents
Calculation method and device for nuclide release activity Download PDFInfo
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Abstract
The invention provides a method and a device for calculating nuclide release activity, wherein the method comprises the following steps: determination of the steady-state specific activity C of nuclide i in a Loop i (0) The method comprises the steps of carrying out a first treatment on the surface of the Obtaining a reservoir I of the nuclear species I in the core i In fuel rod cladding gapsInner fraction f i And a release time period, and calculates a transient release rate R of the nuclear species i from the core to the primary loop i The method comprises the steps of carrying out a first treatment on the surface of the According to the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t); based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Wherein the time t belongs to the target time period. The method and the device for calculating the nuclide release activity can be matched with the SGTR accident consequence restriction criteria specified in the related art, and combine the actual design characteristics of the nuclear power station to calculate Q i Q actually released from nuclear power station i Proximity.
Description
Technical Field
The invention relates to the technical field of pressurized water reactor nuclear power plant design, in particular to a method and a device for calculating nuclide release activity.
Background
The nuclear power station comprises a reactor core, a first loop and a second loop which are sequentially connected, heat generated in the reactor core is transferred to the second loop through the first loop, water in the second loop is evaporated to generate Steam to drive a Steam turbine to generate power, the first loop is particularly communicated with the reactor core and a Steam Generator (SG for short), high-temperature and high-pressure water formed by huge heat energy generated by nuclear fuel fission of the reactor core is transferred to the SG through the first loop, the high-temperature and high-pressure water transfers the heat to cooling water in the second loop through a heat transfer pipe in the SG, and the water after the heat release in the heat transfer pipe returns to the reactor core through the first loop again to circularly perform heat dissipation.
Because of manufacturing defects and long-term operation irradiation, the fuel cladding in the reactor core has a certain breakage rate, the radionuclide in the reactor core can be released into the primary loop, and once the heat transfer tube in the SG is broken, the radionuclide can leak into the secondary loop from the primary loop, so that the radionuclide leaks into the environment, and adverse effects are caused on public health.
At present, only the limit standards which the radioactivity consequences of the nuclear power station need to meet in the event of a steam generator heat transfer tube rupture (Steam Generator Tube Rupture, SGTR) are specified in the relevant regulations, but no matched calculation mode is used for reference. In the prior art, the calculation of the radioactivity result of the nuclear power station under the SGTR accident can only refer to the relevant calculation rule of the developed state of the nuclear power station. However, as the research on accident sources continues, some assumptions and parameters in these reference algorithms have been proven to be impractical, and thus, there is a problem in that the radioactivity consequences calculated by these reference algorithms are greatly different from the actual radioactivity consequences.
Disclosure of Invention
The embodiment of the invention provides a method and a device for calculating nuclide release activity, which are used for solving the problem that the radioactive calculation result of the existing nuclear power station in view of SGTR accidents does not accord with reality.
In order to solve the above technical problems, the present invention provides a method for calculating a nuclide release activity, including:
determination of the steady-state specific activity C of nuclide i in a Loop i (0) The nuclide i is a radionuclide released from the core to the environment;
obtaining a reservoir I of the nuclear species I in the core i The fraction f in the fuel rod cladding gap i And a release time period, and calculates a transient release rate R of the nuclear species i from the core to the primary loop i The R is i And said I i In direct proportion, the R i And f is equal to i Proportional to the ratio;
according to the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t)；
Based on the C i (t) calculating the transmissionActivity Q of the release of the nuclide i to the environment within a target time period after the heat pipe is ruptured i Wherein the time t belongs to the target time period.
Optionally, the method according to C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t) comprising:
by the nuclide balance formula in the first loop and the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t), wherein the nuclide balance formula in the one loop comprises:
wherein the R is i A release rate of the nuclear species i from the core to the primary circuit; the lambda is i A decay constant for the nuclide i; the C is i (t) is the transient specific activity of the nuclide i in the loop at time t, C when t=0 i (0) A steady state specific activity for the nuclide i in the one loop; the M is RCS (t) is the coolant charge of the first circuit at time t; and L (t) is the leakage flow rate of the first loop to the second loop at the moment t.
Optionally, the nuclide i is an inert gas, based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Comprising:
acquiring leakage flow L (t) from the first loop to the second loop at the moment t;
the C is subjected to i The product of (t) and L (t) is taken as the release rate Q of the inert gas to the environment at the moment t i (t)；
The Q is set to i (t) performing an integral calculation for a target period of time to obtain the activity Q of the inert gas released to the environment within the target period of time i 。
Optionally, the nuclide i is halogen or alkali metal, based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Comprising:
according to the steady-state specific activity C of the nuclide i in the loop i (0) Calculating the steady-state specific activity A of the nuclide i in the two loops i (0)；
Acquiring leakage parameter information of the first loop to the second loop at the time t, and calculating the leakage parameter information and the C according to the leakage parameter information i (t) and the A i (0) Transient specific activity A of the nuclide i at the time t in the corresponding two loops i (t)；
Based on the A i (t) calculating the activity Q of the release of the nuclide i to the environment over a target period of time i 。
Optionally, the method is based on the A i (t) calculating the activity Q of the release of the nuclide i to the environment over a target period of time i Comprising:
acquiring a first release parameter of the loop to the environment at the time t, and calculating a second release parameter and the C i (t) the rate Q 'of release of the nuclear species i to the environment at the time t in the corresponding loop' i (t)；
Acquiring a second release parameter of the two loops to the environment at the time t, and calculating the second release parameter and the first release parameter and the A i (t) the rate Q' of release of the nuclear species i to the environment at the time t in the corresponding two loops i (t)；
The Q 'is' i (t) and said Q' i (t) respectively performing integral calculation for a target time period, and taking the sum of the integral calculation as the activity Q of the nuclide i released from the two loops to the environment in the target time period i 。
The invention also provides a device for calculating the nuclide release activity, which comprises:
a determination module for determining the steady-state specific activity C of the nuclide i in a loop i (0) The nuclide i is a radionuclide released from the core to the environment;
a first calculation module for obtaining the accumulation amount I of the nuclide I in the reactor core i The fraction f in the fuel rod cladding gap i And a release time period, and calculates a transient release rate R of the nuclear species i from the core to the primary loop i The R is i And said I i In direct proportion, the R i And f is equal to i Proportional to the ratio;
a second calculation module for calculating the difference between the first and second data according to the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t)；
A third calculation module for based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Wherein the time t belongs to the target time period.
Optionally, the second calculation module is configured to pass the nuclide balance formula and the C in the first loop i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t), wherein the nuclide balance formula in the one loop comprises:
wherein the R is i A release rate of the nuclear species i from the core to the primary circuit; the lambda is i A decay constant for the nuclide i; the C is i (t) is the transient specific activity of the nuclide i in the loop at time t, C when t=0 i (0) A steady state specific activity for the nuclide i in the one loop; the M is RCS (t) is the coolant charge of the first circuit at time t; and L (t) is the leakage flow rate of the first loop to the second loop at the moment t.
Optionally, the nuclide i is an inert gas, and the third calculation module includes:
the first acquisition submodule is used for acquiring leakage flow L (t) of the first loop to the second loop at the moment t;
a first calculation sub-module for calculating the C i The product of (t) and L (t) is taken as the release rate Q of inert gas to the environment at the moment t i (t)；
A second calculation sub-module for calculating the Q i (t) performing an integral calculation for a target period of time to obtain the activity Q of the inert gas released to the environment within the target period of time i 。
Optionally, the nuclide i is halogen or alkali metal, and the third calculation module includes:
a third calculation sub-module for calculating a steady state specific activity C of the nuclide i in the loop i (0) Calculating the steady-state specific activity A of the nuclide i in the two loops i (0)；
A fourth calculation sub-module for obtaining the leakage parameter information of the first loop to the second loop at the time t, and calculating the leakage parameter information and the C according to the leakage parameter information i (t) and the A i (0) Transient specific activity A of the nuclide i at the time t in the corresponding two loops i (t)；
A fifth calculation sub-module for based on the A i (t) calculating the activity Q of the release of the nuclide i to the environment over a target period of time i 。
Optionally, the fifth calculation sub-module includes:
a first calculation unit for acquiring a first release parameter of the loop to the environment at the time t, and calculating the first release parameter and the C i (t) the rate Q 'of release of the nuclear species i to the environment at the time t in the corresponding loop' i (t)；
A second calculation unit for acquiring a second release parameter of the second loop to the environment at the time t, and calculating the first release parameter and the A i (t) the nuclide i in the corresponding two loops is directed to the environment at the time tRate of release Q' i (t)；
A third calculation unit for calculating the Q' i (t) and said Q' i (t) respectively performing integral calculation for a target time period, and taking the sum of the integral calculation as the activity Q of the nuclide i released from the two loops to the environment in the target time period i 。
The embodiment of the invention also provides electronic equipment, which comprises a processor, a memory and a computer program stored on the memory and capable of running on the processor, wherein the computer program realizes the steps of the method for calculating the nuclide release activity when being executed by the processor.
The embodiment of the invention also provides a computer readable storage medium, wherein the computer readable storage medium is stored with a computer program, and the computer program realizes the steps of the nuclide release activity calculation method when being executed by a processor.
In an embodiment of the present invention, the steady state specific activity C of the nuclide i in a loop is determined by i (0) The nuclide i is a radionuclide released from the core to the environment; obtaining a reservoir I of the nuclear species I in the core i The fraction f in the fuel rod cladding gap i And a release time period, and calculates a transient release rate R of the nuclear species i from the core to the primary loop i The R is i And said I i In direct proportion, the R i And f is equal to i Proportional to the ratio; according to the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t); based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Wherein the time t belongs to the target time period. Thus, based on R i Corresponding C i (t) the calculated activity Q of the release of the nuclide i to the environment i The method is close to the actual activity of the nuclide i released to the environment in the nuclear power station, and the accuracy of calculating the activity of the nuclide released to the environment can be improved. In addition, the invention also relates to SGTR matters in relevant regulationsThe consequence restriction criteria are matched, so that the nuclear power station is beneficial to the calculation standardization of the nuclide release activity of the nuclear power station under SGTR accidents.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings that are needed in the description of the embodiments of the present invention will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and other drawings may be obtained according to these drawings without inventive effort to a person of ordinary skill in the art.
FIG. 1 is a flowchart of a method for calculating a nuclide release activity according to an embodiment of the present invention;
FIG. 2 is a schematic structural diagram of a nuclear power plant as applied to various embodiments of the present invention;
FIG. 3 is a flowchart of a method for calculating a nuclide release activity according to another embodiment of the present invention;
FIG. 4 is a block diagram of a computing device for nuclide release activity according to an embodiment of the present invention;
FIG. 5 is a block diagram of a computing device for nuclide release activity according to another embodiment of the present invention;
FIG. 6 is a block diagram of a computing device for nuclide release activity according to another embodiment of the present invention;
FIG. 7 is a block diagram of a fifth calculation sub-module of FIG. 6;
fig. 8 is a schematic diagram of a hardware structure of an electronic device implementing various embodiments of the present invention.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and fully with reference to the accompanying drawings, in which it is evident that the embodiments described are some, but not all embodiments of the invention. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
Referring to fig. 1, fig. 1 is a flowchart of a method for calculating a nuclide release activity according to an embodiment of the invention, as shown in fig. 1, including the following steps:
step 101: determination of the steady-state specific activity C of nuclide i in a Loop i (0) The nuclide i is a radionuclide released from the core to the environment.
Referring to fig. 2, a schematic structural diagram of a nuclear power plant according to various embodiments of the present invention is shown. The basic accidents to be considered in the design process of the nuclear power station comprise main steam pipeline cracking accidents (main steam line break accident, MSLB for short), main water supply pipeline cracking accidents, pump shaft blocking and pump shaft cracking of a reactor coolant pump, control rod ejection accidents, SGTR and the like, and different accidents have key input parameters, and the accidents have mutual relevance, for example: the same parameters need to be utilized between two different benchmark incidents. In the embodiment of the invention, in order to simplify the difficulty of unifying parameters of different reference accidents in a nuclear power station, the input of a calculation method of the nuclide release activity under the SGTR accident is carried out: steady state specific activity C of nuclide i in a loop i (0) Consistent with other baseline incidents, specifically, steady state specific activities of different species in a loop are shown in table 1.
TABLE 1 steady state specific activity of nuclides in the first Loop (units: GBq/t)
Table 1 includes radionuclides released from the core to the environment, and the nuclide i may be any one of the nuclides in table 1. The steady state specific activity of a nuclear species in a loop coolant, as shown in table 1, is a result of equivalent normalization to the data parameters of other baseline incidents.
Step 102: obtaining a reservoir I of the nuclear species I in the core i The fraction f in the fuel rod cladding gap i And a release time period, and calculates the nuclide i from the core to the coreTransient release rate R of the first loop i The R is i And said I i In direct proportion, the R i And f is equal to i Proportional to the ratio.
In the embodiment of the invention, a transient change of nuclide activity in a loop coolant is calculated by adopting an accident concurrent iodine spike model. As SGTR accidents result in core power transients and a loop pressure transient, the rate of release of nuclear i from the fuel cladding to a loop increases, and conservative consideration is given to all nuclear i within the broken fuel rod gap being released into a loop all the way through the transient time.
The transient release rate of nuclide i over the release period is:
wherein the R is i The unit is Bq/s which is the release rate of nuclide i from the reactor core to a loop under transient conditions; the I is i The unit is Bq for the accumulation of nuclide i in the core; said f i Is the fraction of nuclide i in the cladding gap; the eta is the damaged share of the fuel cladding; the Δt is the release duration of the nuclide i.
I i The reactor core is obtained by acquiring reactor core reaction power, fuel burnup, reactor core arrangement information and the like as inputs through professional software in the field of nuclear engineering, so that the accumulation change value of the nuclide i in each stage of reactor core can be determined.
f i Is to follow the share value of nuclide i in the cladding gap in the prior SGTR calculation mode, f i Depending on the volatility characteristics of each fission product in the core, it can be determined through multiple experimental and empirical accumulation in the same core.
η is the upper limit value 0.25% required by China in the operation technical specification of the nuclear power station for the damage of the cladding, the damaged portion of the cladding is not more than 0.25% under the actual SGTR accident, and the release activity Q finally obtained by calculation is carried out by adopting 0.25% i Not less than the actual release activity, in the calculated release activity Q i When the specification is satisfied, it is possible to ensure that the actual released activity of the nuclear power plant satisfies the specification.
Δt is the length of time that the nuclear species i leaks from the fuel rod cladding gap into a circuit during which all of the nuclear species i in the fuel rod cladding gap are released into a circuit. In the examples of the present invention, Δt takes an empirically conserved value of 8 hours.
By combining the input parameters with the formula (1), the release rate R of the nuclide i from the reactor core to the primary loop can be calculated i 。
Step 103: according to the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t)。
At t=0, the SGTR event does not occur, the loop is in steady state, C i (0) Is the steady state specific activity of nuclide i in a loop.
After t=0, SGTR accident occurs, the loop is in transient state, C i And (t) is the transient specific activity of the nuclide i in the primary loop at the moment t. Wherein at time t, influence C i The parameters of (t) include:
the leakage amount of nuclide i in the primary circuit to the secondary circuit through the broken heat transfer tube is more C i The lower (t), the less C the leakage i The higher (t).
A loop receives the nuclear i leaking from the core, and the leak rate R of the nuclear i from the core to the loop i Already in step 102, R i The larger C i The larger (t), R i Smaller C i The smaller (t).
In addition, the nuclide i in the loop decays, and the larger the decay constant of the nuclide i is C i (t) the higher the decay constant of nuclide i, the smaller C i The lower (t).
By determining the above-mentioned influence C i Parameters of (t) and R determined in step 102 i Thereby being capable of calculating C i (t)。
Step 104: based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Wherein the time tThe score belongs to the target time period.
After the nuclide i leaks from the primary circuit to the secondary circuit, the secondary circuit entrains and releases the nuclide i in the secondary circuit into the environment in the process of releasing steam to the environment, and in the prior art, a plurality of calculation modes can be based on C i (t) calculating Q i And will not be described in detail herein.
In the embodiment of the present invention, the end time of the SGTR accident is the start time plus Δt, and the target time period is the time period between the start time and the end time of the SGTR accident.
In the embodiment of the invention, the steady-state specific activity C of the nuclide i in a loop is determined i (0) The nuclide i is a radionuclide released from the core to the environment; obtaining a reservoir I of the nuclear species I in the core i The fraction f in the fuel rod cladding gap i And a release time period, and calculates a transient release rate R of the nuclear species i from the core to the primary loop i The R is i And said I i In direct proportion, the R i And f is equal to i Proportional to the ratio; according to the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t); based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Wherein the time t belongs to the target time period. Thus, based on R i Corresponding C i (t) the calculated activity Q of the release of the nuclide i to the environment i The method is close to the actual activity of the nuclide i released to the environment in the nuclear power station, and the accuracy of calculating the activity of the nuclide released to the environment can be improved. In addition, the invention is matched with the restrictive criterion for the SGTR accident outcome in the related regulations, thereby being beneficial to the calculation standardization of the nuclear power station for the nuclide release activity under the SGTR accident.
Referring to fig. 3, fig. 3 is a flowchart illustrating a method for calculating a nuclide release activity according to another embodiment of the present invention, which is different from the embodiment shown in fig. 1 in that the present embodiment calculates C by using a nuclide balance formula in the loop i (t). As shown in fig. 3, the method comprises the following steps:
step 301: determination of the steady-state specific activity C of nuclide i in a Loop i (0) The nuclide i is a radionuclide released from the core to the environment.
Step 302: obtaining a reservoir I of the nuclear species I in the core i Share f in the cladding gap i And a release time period, and calculates a release rate R of the nuclear species i from the core to the primary circuit i The R is i And said I i In direct proportion, the R i And f is equal to i Proportional to the ratio.
The implementation process and the beneficial effect of step 301 may correspond to those described in step 101, and the implementation process and the beneficial effect of step 302 may correspond to those described in step 102, which are not repeated here.
Step 303: by the nuclide balance formula in the first loop and the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t), wherein the nuclide balance formula in the one loop comprises:
wherein the R is i A transient release rate for the nuclear species i from the core to the primary circuit; the lambda is i A decay constant for the nuclide i; the C is i (t) is the transient specific activity of the nuclide i in the loop at time t, C when t=0 i (0) A steady state specific activity for the nuclide i in the one loop; the M is RCS (t) is the coolant charge of the first circuit at time t in kg; and L (t) is the leakage flow rate of the first loop to the second loop at the moment t, and the unit is kg/s.
The result can be obtained by the formula (2):
Wherein:
λ i the physical characteristic of the nuclide i is obtained from the nuclide i itself, and the lambda can be uniquely determined after the nuclide i is determined i 。
M RCS (t) is changed in the SGTR accident process and is calculated by a thermal hydraulic analysis program through professional software in the field of nuclear engineering, and M is calculated by different nuclear power plants RCS And (t) different, each nuclear power station needs professional software to be calculated through a thermal hydraulic analysis program and specific input parameters in the actual nuclear power station.
L (t) and M RCS (t) similarly, changes during SGTR events, as well as calculated by thermal hydraulic analysis programs by specialized software in the field of nuclear engineering.
C obtained by the above parameters and step 301 i (0) And R obtained in step 302 i Combining (3) to calculate C i (t)。
Because each input parameter is the actual operation parameter of the nuclear power station, the hypothetical parameter is eliminated, the calculation is tightly combined with the actual design characteristics of the nuclear power station, and the calculated C is obtained i (t) and actual C in Nuclear Power plant i (t) the difference is small.
Step 304: based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Wherein the time t belongs to the target time period.
In an alternative embodiment, the nuclide i is an inert gas, the method is based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Comprising:
acquiring leakage flow L (t) from the first loop to the second loop at the moment t;
the C is subjected to i The product of (t) and L (t) is taken asThe release rate Q of the inert gas to the environment at the time t i (t)；
The Q is set to i (t) performing integral calculation for a target time period to obtain activity Q of the inert gas released to the environment in the target time period i 。
In this embodiment, L (t) is calculated in step 303 by the thermohydraulic analysis program, and will not be described again. After the inert gas leaks from the first loop to the second loop, the inert gas is released into the environment by the second loop in the process of radiating heat to the environment, the inert gas flow leaked from the first loop to the second loop at the moment t is the inert gas flow L (t) leaked from the second loop to the environment, and the activity of the leaked inert gas is the same as the transient activity of the inert gas in the first loop, so that the activity Q of the inert gas leaked from the second loop to the environment at the moment t i (t) is C i Product of (t) and L (t).
the time t belongs to the target time period by the method of Q i (t) performing integration for a target time period, namely calculating the total activity released to the environment during the target time period by the inert gas, wherein the specific formula is as follows:
wherein t1 is the start time of the target time period, t2 is the end time of the target time period, and t is between t1 and t 2.
By determining the leakage flow rate L (t) of the first loop to the second loop at each moment in the target time period and the transient specific activity C of the inert gas in the next loop at each moment in the target time period i (t) so that the total activity Q of the inert gas released to the environment in the target period of time can be calculated by the formula (4) i 。
In the embodiment, the flow rate of the inert gas leaking from the first loop to the second loop is directly used as the flow rate of the inert gas leaking from the second loop to the environment by the characteristic of the inert gas, and the physical characteristic that the inert gas is not retained by water is combined, so that the calculation Q is improved i Is not limited to the above-described embodiments.
In other embodiments, the activity of the inert gas released to the environment may be calculated in other ways, and the present invention is not limited to the above embodiments.
In addition, the leakage flow L (t) of the first loop to the second loop at the moment t is obtained; the C is subjected to i The product of (t) and L (t) is taken as the activity Q of the inert gas released to the environment at the moment t i (t); the Q is set to i (t) performing integral calculation for a target time period to obtain activity Q of the inert gas released to the environment in the target time period i The same applies to the embodiment shown in fig. 1 and has the same advantageous effects.
In another alternative embodiment, the nuclide i is a halogen or an alkali metal, the C-based i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Comprising:
according to the steady-state specific activity C of the nuclide i in the loop i (0) Calculating the steady-state specific activity A of the nuclide i in the two loops i (0)；
Acquiring leakage parameter information of the first loop to the second loop at the time t, and calculating the leakage parameter information and the C according to the leakage parameter information i (t) and the A i (0) Transient specific activity A of the nuclide i at time t in the corresponding two loops i (t)；
Based on the A i (t) calculating the activity Q of the release of the nuclide i to the environment within a target time period i 。
In this embodiment, before the SGTR accident does not occur, the first loop and the second loop are in a homostable state, and conform to the mass conservation formula of the nuclide:
The steady state specific activity of the nuclide i in the two-loop can be deduced from equation (5) as:
wherein A is i (0) The steady-state specific activity of the nuclide i in the secondary loop is expressed as Bq/kg; l (L) P/S The unit is kg/s for the leakage flow of the previous loop to the second loop which does not occur in SGTR accident; m is M SG (0) The unit of the water content of the two loops before SGTR accident is kg; f (F) SG_blow The sewage discharge flow of the SG before SGTR accident does not occur is in kg/s; SG (SG) cyclerate The pollution discharge circulation rate of the SG before SGTR accident does not occur; and e is a filtering coefficient of the SG sewage system for the nuclide i in the sewage circulation flow.
L P/S Is constant before the SGTR accident occurs, and is determined by the SG manufacturing process and the operating conditions.
M SG (0) The stability of the SGTR is maintained in a stable range before the SGTR accident, and the SGTR accident is calculated by professional software in the field of nuclear engineering by using a thermal hydraulic analysis program.
F SG_blow And SG (all) cyclerate Is a design parameter of the nuclear power station, the nuclear power station discharges the water in the two loops through continuous circulation before SGTR accident occurs so as to ensure the water quality in the two loops, F SG_blow Is a fixed value, SG cyclerate Is a fixed ratio.
By determining the above-mentioned parameters, and C obtained in step 301 i (0) The steady-state specific activity A of the nuclide i in the secondary loop can be calculated by combining the formula (6) i (0)。
Thereafter, after an SGTR event, due to the transient specific activity A of nuclide i in the two loops i (t) calculating the transient specific activity A of the nuclide i in the two loops according to the following formula, wherein the transient specific activity A is related to the leakage flow of the first loop to the second loop, the decay of the nuclide i in the second loop and the entrainment of the second loop and the ambient evaporative heat dissipation i (t):
Wherein the A i (t) is the transient specific activity of the nuclide i in the second loop at time t, and the unit is Bq/kg; the L (t) is the leakage flow rate from the first loop to the second loop at the moment t, and the unit is kg/s; the lambda is i A decay constant for the nuclide i; the M is SG (t) is the water content of the second loop at the moment t, and the unit is kg; the m is v The unit is kg/s of steam flow released by an atmospheric release valve of the SG; the L is break The unit is kg/s for the break flow of the heat transfer tube in the SG; the CR is the entrainment coefficient of nuclide i in steam; and ff is the flash evaporation share of the break-through flow of the heat transfer tube.
The transient specific activity A of the nuclide i in the two loops can be deduced by the formula (7) i (t) is:
wherein,,
the h is 1 The enthalpy value of water in a loop is J/kg; the h is 2 The enthalpy value of water in the second loop is J/kg; and r is the vaporization latent heat of water in the second loop, and the unit is J/kg.
M SG (t)、L(t)、L break And m v The M is obtained by calculating through a thermal hydraulic analysis program by professional software in the field of nuclear engineering and M is obtained by calculating different nuclear power stations SG (t) and m v Different, each nuclear power station needs professional software to be calculated through a thermal hydraulic analysis program and specific input parameters in the actual nuclear power station.
CR depends on the physical properties of the species i, and can be uniquely determined by determining the species i.
ff requires indirect detection of h 1 、h 2 And r, calculating.
By determining the above-mentioned parameters and byA obtained by the formula (6) i (0) And C, obtained by step 303 i (t) calculating the transient specific activity A of the nuclide i in the two loops by combining the formula (8) i (t)。
Finally, based on the A i (t) calculating the activity Q of the release of the nuclide i to the environment within a target time period i 。
The A is based on i (t) calculating the activity Q of the release of the nuclide i to the environment within a target time period i May include:
acquiring a first release parameter of the loop to the environment at the time t, and calculating a second release parameter and the C i (t) the rate Q 'of release of the nuclear species i to the environment at time t in the corresponding loop' i (t)；
Acquiring a second release parameter of the two loops to the environment at the time t, and calculating the second release parameter and the first release parameter and the A i (t) the rate Q' of release of the nuclear species i to the environment at time t in the corresponding two loops i (t)；
The Q 'is' i (t) and said Q' i (t) respectively performing integral calculation for a target time period, and taking the sum of the integral calculation as activity Q of the nuclide i released from the two loops to the environment in the target time period i 。
In this embodiment, Q' i (t) and Q i The calculation formula of (t) is as follows:
Q′ i (t)＝L break ·ff·C i (t) 9
Q″ i (t)＝(F′ steam -L break ·ff)·A i (t). CR type (10)
Wherein the L is break The unit is kg/s for the break flow of the heat transfer tube in the SG; the ff is the flash evaporation share of the heat transfer tube break flow, the calculation of the ff is the same as the formula (7), and the description is omitted here; the C is i (t) is the transient specific activity of the nuclide i in a loop at the moment t, and the unit is Bq/kg; said F' steam Steam flow released to the environment by the atmosphere release valve of the broken SG is expressed in kg/s; by a means ofThe A is i And (t) is the transient specific activity of the nuclide i in the two loops at the moment t, and the unit is Bq/kg.
Q′ i (t) is the flash evaporation rate of the break flow of the nuclide i from the primary loop through the heat transfer pipe at the moment t, and is directly released into the environment without being mixed with secondary loop water, aiming at Q '' i (t) performing an integration calculation for a target period of time:
Q″ i (t) the rate of entrainment release into the environment during release of steam into the environment by mixing the nuclide i in the break flow of the non-flash evaporation part at the moment t with water in the second loop, and aiming at Q' i (t) performing an integration calculation for a target period of time:
release Activity Q 'of flash portion of nuclide i' i Adding the release activity Q' of the non-flash part i The sum of the values is the activity Q of the release of the nuclide i to the environment i 。
The A-based method i (t) calculating the activity Q of the release of the nuclide i to the environment within a target time period i The calculation may be performed by other methods in the existing algorithm, and is not limited to the one described in this embodiment mode.
In this embodiment, in the case where the nuclide i is halogen or alkali metal, the activity Q of calculating the release of the nuclide i to the environment in the target time period is improved by calculating the steady-state activity and the transient-state activity of the nuclide i in the two loops on the basis of obtaining the steady-state activity and the transient-state activity of the nuclide i in the one loop i Is a function of the accuracy of the (c).
In other embodiments, the activity of halogen or alkali metal released to the environment may be calculated in other ways, and the present invention is not limited to the above embodiments.
In addition, the method is based on the steady state specific activity C of the nuclide i in the primary loop i (0) Calculating the steady-state specific activity A of the nuclide i in the two loops i (0) The method comprises the steps of carrying out a first treatment on the surface of the Acquiring leakage parameter information of the first loop to the second loop at the time t, and calculating the leakage parameter information and the C according to the leakage parameter information i (t) and the A i (0) Transient specific activity A of the nuclide i at time t in the corresponding two loops i (t); based on the A i (t) calculating the activity Q of the release of the nuclide i to the environment within a target time period i The same applies to the embodiment shown in fig. 1 and has the same advantageous effects.
In this embodiment, the steady-state specific activity C of the nuclide i in a loop is calculated by using the nuclide balance formula in a loop i (t) each input parameter is the actual operation parameter of the nuclear power station, so that the hypothetical parameters are eliminated, the actual design characteristics of the nuclear power station are closely combined, and the calculated C is obtained i (t) and actual C i (t) approach, further basing the follow-up on C i (t) the activity Q of the nuclide i released into the environment i And actual Q i Proximity.
Referring to fig. 4, fig. 4 is a block diagram of a calculating apparatus for nuclide release activity according to an embodiment of the present invention, as shown in fig. 4, the calculating apparatus for nuclide release activity includes: a determination module 401, a first calculation module 402, a second calculation module 403, and a third calculation module 404;
a determination module 401 for determining the steady-state specific activity C of the nuclide i in a loop i (0) The nuclide i is a radionuclide released from the core to the environment;
a first calculation module 402 for obtaining a cumulative amount I of the nuclear species I in the core i The fraction f in the fuel rod cladding gap i And a release time period, and calculates a transient release rate R of the nuclear species i from the core to the primary loop i The R is i And said I i In direct proportion, the R i And f is equal to i Proportional to the ratio;
a second calculation module 403, configured to, according to the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t)；
A third calculation module 404 for based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Wherein the time t belongs to the target time period.
Optionally, the second calculation module 403 is configured to pass the nuclide balance formula and the C in the first loop i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t), wherein the nuclide balance formula in the one loop comprises:
wherein the R is i A release rate of the nuclear species i from the core to the primary circuit; the lambda is i A decay constant for the nuclide i; the C is i (t) is the transient specific activity of the nuclide i in the loop at time t, C when t=0 i (0) A steady state specific activity for the nuclide i in the one loop; the M is RCS (t) is the coolant charge of the first circuit at time t; and L (t) is the leakage flow rate of the first loop to the second loop at the moment t.
Optionally, referring to fig. 5, the nuclide i is an inert gas, and the third calculation module 404 includes:
a first obtaining submodule 4041, configured to obtain a leakage flow L (t) of the first loop to the second loop at the time t;
a first calculation submodule 4042 for integrating the C i The product of (t) and L (t) is taken as the release rate Q of inert gas to the environment at the moment t i (t)；
A second calculation submodule 4043 for converting said Q i (t) performing an integral calculation for the target periodObtaining activity Q of the inert gas released to the environment in the target time period i 。
Optionally, referring to fig. 6, the nuclide i is halogen or alkali metal, and the third calculation module 404 includes:
a third calculation sub-module 4044 for calculating a steady state specific activity C of the nuclear species i in the loop i (0) Calculating the steady-state specific activity A of the nuclide i in the two loops i (0)；
A fourth calculation submodule 4045 for obtaining leakage parameter information of the first loop to the second loop at the time t, and calculating the leakage parameter information and the C according to the leakage parameter information i (t) and the A i (0) Transient specific activity A of the nuclide i at the time t in the corresponding two loops i (t)；
A fifth calculation sub-module 4046 for based on said a i (t) calculating the activity Q of the release of the nuclide i to the environment over a target period of time i 。
Optionally, referring to fig. 7, the fifth calculating submodule 4046 includes:
a first calculating unit 40461 for acquiring a first release parameter of the loop to the environment at the time t and calculating a first release parameter and the C i (t) the rate Q 'of release of the nuclear species i to the environment at the time t in the corresponding loop' i (t)；
A second calculating unit 40462 for acquiring a second release parameter of the second loop to the environment at the time t and calculating the first release parameter and the A i (t) the rate Q' of release of the nuclear species i to the environment at the time t in the corresponding two loops i (t)；
A third calculation unit 40463 for dividing the Q' i (t) and said Q' i (t) respectively performing integral calculation for a target time period, and taking the sum of the integral calculation as the activity Q of the nuclide i released from the two loops to the environment in the target time period i 。
The nuclide release activity calculating device 400 can implement each process implemented by the nuclide release activity calculating device in the method embodiments of fig. 1 to 3, and for avoiding repetition, a description is omitted here.
The apparatus 400 for calculating the nuclide release activity according to the embodiment of the invention is based on the sum R i Corresponding C i (t) the calculated activity Q of the release of the nuclide i to the environment i The method is close to the actual activity of the nuclide i released to the environment in the nuclear power station, and the accuracy of calculating the activity of the nuclide released to the environment can be improved. In addition, the invention is matched with the restrictive criterion for the SGTR accident outcome in the related regulations, thereby being beneficial to the calculation standardization of the nuclear power station for the nuclide release activity under the SGTR accident.
Fig. 8 is a schematic diagram of a hardware structure of an electronic device implementing various embodiments of the present invention.
The electronic device 800 includes, but is not limited to: radio frequency unit 801, network module 802, audio output unit 803, input unit 804, sensor 805, display unit 806, user input unit 807, interface unit 808, memory 809, processor 810, and power supply 811. It will be appreciated by those skilled in the art that the electronic device structure shown in fig. 8 is not limiting of the electronic device and that the electronic device may include more or fewer components than shown, or may combine certain components, or a different arrangement of components. In the embodiment of the invention, the electronic equipment comprises, but is not limited to, a mobile phone, a tablet computer, a notebook computer, a palm computer, a vehicle-mounted terminal, a wearable device, a pedometer and the like.
Wherein the processor 810 is configured to determine a steady state specific activity C of the nuclear species i in a loop i (0) The nuclide i is a radionuclide released from the core to the environment; obtaining a reservoir I of the nuclear species I in the core i The fraction f in the fuel rod cladding gap i And a release time period, and calculates a transient release rate R of the nuclear species i from the core to the primary loop i The R is i And said I i In direct proportion, the R i And f is equal to i Proportional to the ratio; according to the C i (0) Calculating the R i Corresponding to the first loopTransient specific activity C of the nuclide i in the road at time t i (t); based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Wherein the time t belongs to the target time period.
Optionally, said processor 810 is executing said processing according to said C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i In the step of (t), comprising: by the nuclide balance formula in the first loop and the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t), wherein the nuclide balance formula in the one loop comprises:
Wherein the R is i A release rate of the nuclear species i from the core to the primary circuit; the lambda is i A decay constant for the nuclide i; the C is i (t) is the transient specific activity of the nuclide i in the loop at time t, C when t=0 i (0) A steady state specific activity for the nuclide i in the one loop; the M is RCS (t) is the coolant charge of the first circuit at time t; and L (t) is the leakage flow rate of the first loop to the second loop at the moment t.
Optionally, the nuclide i is an inert gas, and the processor 810 is configured to perform the following steps based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Comprises the following steps: acquiring leakage flow L (t) from the first loop to the second loop at the moment t; the C is subjected to i The product of (t) and L (t) is taken as the release rate Q of the inert gas to the environment at the moment t i (t); the Q is set to i (t) performing an integral calculation for a target period of time to obtain the activity Q of the inert gas released to the environment within the target period of time i 。
Optionally, the nuclide i is halogen or alkali metal, and the processor 810 is configured to i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Comprises the following steps: according to the steady-state specific activity C of the nuclide i in the loop i (0) Calculating the steady-state specific activity A of the nuclide i in the two loops i (0) The method comprises the steps of carrying out a first treatment on the surface of the Acquiring leakage parameter information of the first loop to the second loop at the time t, and calculating the leakage parameter information and the C according to the leakage parameter information i (t) and the A i (0) Transient specific activity A of the nuclide i at the time t in the corresponding two loops i (t); based on the A i (t) calculating the activity Q of the release of the nuclide i to the environment over a target period of time i 。
Optionally, the processor 810 is executing on the base of the a i (t) calculating the activity Q of the release of the nuclide i to the environment over a target period of time i Comprises the following steps: acquiring a first release parameter of the loop to the environment at the time t, and calculating a second release parameter and the C i (t) the rate Q 'of release of the nuclear species i to the environment at the time t in the corresponding loop' i (t)；
Acquiring a second release parameter of the two loops to the environment at the time t, and calculating the second release parameter and the first release parameter and the A i (t) the rate Q' of release of the nuclear species i to the environment at the time t in the corresponding two loops i (t)；
The Q 'is' i (t) and said Q' i (t) respectively performing integral calculation for a target time period, and taking the sum of the integral calculation as the activity Q of the nuclide i released from the two loops to the environment in the target time period i 。
The electronic device 800 can implement each process implemented by the computing device of the nuclide release activity in the foregoing embodiment, and in order to avoid repetition, a description thereof will be omitted.
The electronic device 800 of the embodiment of the invention is based on the R-base i Corresponding C i (t) the calculated activity Q of the release of the nuclide i to the environment i The method is close to the actual activity of the nuclide i released to the environment in the nuclear power station, and the accuracy of calculating the activity of the nuclide released to the environment can be improved. In addition, the invention is matched with the restrictive criterion for the SGTR accident outcome in the related regulations, thereby being beneficial to the calculation standardization of the nuclear power station for the nuclide release activity under the SGTR accident.
It should be understood that, in the embodiment of the present invention, the radio frequency unit 801 may be used for receiving and transmitting signals during the process of receiving and transmitting information or communication, specifically, receiving downlink data from a base station, and then processing the received downlink data by the processor 810; and, the uplink data is transmitted to the base station. In general, the radio frequency unit 801 includes, but is not limited to, an antenna, at least one amplifier, a transceiver, a coupler, a low noise amplifier, a duplexer, and the like. In addition, the radio frequency unit 801 may also communicate with networks and other devices through a wireless communication system.
The electronic device provides wireless broadband internet access to the user through the network module 802, such as helping the user to send and receive e-mail, browse web pages, access streaming media, and the like.
The audio output unit 803 may convert audio data received by the radio frequency unit 801 or the network module 802 or stored in the memory 809 into an audio signal and output as sound. Also, the audio output unit 803 may also provide audio output (e.g., a call signal reception sound, a message reception sound, etc.) related to a specific function performed by the electronic device 800. The audio output unit 803 includes a speaker, a buzzer, a receiver, and the like.
The input unit 804 is used for receiving an audio or video signal. The input unit 804 may include a graphics processor (Graphics Processing Unit, GPU) 8041 and a microphone 8042, the graphics processor 8041 processing image data of still pictures or video obtained by an image capturing apparatus (such as a camera) in a video capturing mode or an image capturing mode. The processed image frames may be displayed on the display unit 806. The image frames processed by the graphics processor 8041 may be stored in the memory 809 (or other storage medium) or transmitted via the radio frequency unit 801 or the network module 802. The microphone 8042 can receive sound, and can process such sound into audio data. The processed audio data may be converted into a format output that can be transmitted to the mobile communication base station via the radio frequency unit 801 in case of a telephone call mode.
The electronic device 800 also includes at least one sensor 805 such as a light sensor, a motion sensor, and other sensors. Specifically, the light sensor includes an ambient light sensor and a proximity sensor, wherein the ambient light sensor can adjust the brightness of the display panel 8061 according to the brightness of ambient light, and the proximity sensor can turn off the display panel 8061 and/or the backlight when the electronic device 800 moves to the ear. As one of the motion sensors, the accelerometer sensor can detect the acceleration in all directions (generally three axes), and can detect the gravity and direction when stationary, and can be used for recognizing the gesture of the electronic equipment (such as horizontal and vertical screen switching, related games, magnetometer gesture calibration), vibration recognition related functions (such as pedometer and knocking), and the like; the sensor 805 may also include a fingerprint sensor, a pressure sensor, an iris sensor, a molecular sensor, a gyroscope, a barometer, a hygrometer, a thermometer, an infrared sensor, etc., which are not described herein.
The display unit 806 is used to display information input by a user or information provided to the user. The display unit 806 may include a display panel 8061, and the display panel 8061 may be configured in the form of a liquid crystal display (Liquid Crystal Display, LCD), an Organic Light-Emitting Diode (OLED), or the like.
The user input unit 807 is operable to receive input numeric or character information and to generate key signal inputs related to user settings and function controls of the electronic device. In particular, the user input unit 807 includes a touch panel 8071 and other input devices 8072. Touch panel 8071, also referred to as a touch screen, may collect touch operations thereon or thereabout by a user (e.g., operations of the user on touch panel 8071 or thereabout using any suitable object or accessory such as a finger, stylus, etc.). The touch panel 8071 may include two parts, a touch detection device and a touch controller. The touch detection device detects the touch azimuth of a user, detects a signal brought by touch operation and transmits the signal to the touch controller; the touch controller receives touch information from the touch detection device, converts it into touch point coordinates, sends the touch point coordinates to the processor 810, and receives and executes commands sent from the processor 810. In addition, the touch panel 8071 may be implemented in various types such as resistive, capacitive, infrared, and surface acoustic wave. In addition to the touch panel 8071, the user input unit 807 can include other input devices 8072. In particular, other input devices 8072 may include, but are not limited to, physical keyboards, function keys (e.g., volume control keys, switch keys, etc.), trackballs, mice, joysticks, and so forth, which are not described in detail herein.
Further, the touch panel 8071 may be overlaid on the display panel 8061, and when the touch panel 8071 detects a touch operation thereon or thereabout, the touch operation is transmitted to the processor 810 to determine a type of touch event, and then the processor 810 provides a corresponding visual output on the display panel 8061 according to the type of touch event. Although in fig. 8, the touch panel 8071 and the display panel 8061 are two independent components for implementing the input and output functions of the electronic device, in some embodiments, the touch panel 8071 and the display panel 8061 may be integrated to implement the input and output functions of the electronic device, which is not limited herein.
The interface unit 808 is an interface to which an external device is connected to the electronic apparatus 800. For example, the external devices may include a wired or wireless headset port, an external power (or battery charger) port, a wired or wireless data port, a memory card port, a port for connecting a device having an identification module, an audio input/output (I/O) port, a video I/O port, an earphone port, and the like. The interface unit 808 may be used to receive input (e.g., data information, power, etc.) from an external device and transmit the received input to one or more elements within the electronic apparatus 800 or may be used to transmit data between the electronic apparatus 800 and an external device.
The memory 809 can be used to store software programs as well as various data. The memory 809 may mainly include a storage program area that may store an operating system, application programs required for at least one function (such as a sound playing function, an image playing function, etc.), and a storage data area; the storage data area may store data (such as audio data, phonebook, etc.) created according to the use of the handset, etc. In addition, the memory 809 may include high speed random access memory, and may also include non-volatile memory, such as at least one magnetic disk storage device, flash memory device, or other volatile solid state storage device.
The processor 810 is a control center of the electronic device, connects various parts of the entire electronic device using various interfaces and lines, and performs various functions of the electronic device and processes data by running or executing software programs and/or modules stored in the memory 809, and invoking data stored in the memory 809, thereby performing overall monitoring of the electronic device. The processor 810 may include one or more processing units; preferably, the processor 810 may integrate an application processor that primarily handles operating systems, user interfaces, applications, etc., with a modem processor that primarily handles wireless communications. It will be appreciated that the modem processor described above may not be integrated into the processor 810.
The electronic device 800 may also include a power supply 811 (e.g., a battery) for powering the various components, and the power supply 811 may preferably be logically coupled to the processor 810 through a power management system that provides for managing charge, discharge, and power consumption.
In addition, the electronic device 800 includes some functional modules, which are not shown, and will not be described herein.
Preferably, the embodiment of the present invention further provides an electronic device, including a processor 810, a memory 809, and a computer program stored in the memory 809 and capable of running on the processor 810, where the computer program when executed by the processor 810 implements each process of the above embodiment of the method for calculating the nuclide release activity, and the same technical effects can be achieved, and for avoiding repetition, a detailed description is omitted herein.
The embodiment of the invention also provides a computer readable storage medium, on which a computer program is stored, which when executed by a processor, implements the processes of the above-mentioned embodiment of the method for calculating the nuclide release activity, and can achieve the same technical effects, so that repetition is avoided, and no further description is given here. Wherein the computer readable storage medium is selected from Read-Only Memory (ROM), random access Memory (Random Access Memory, RAM), magnetic disk or optical disk.
It should be noted that, in this document, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus. Without further limitation, an element defined by the phrase "comprising one … …" does not exclude the presence of other like elements in a process, method, article, or apparatus that comprises the element.
From the above description of the embodiments, it will be clear to those skilled in the art that the above-described embodiment method may be implemented by means of software plus a necessary general hardware platform, but of course may also be implemented by means of hardware, but in many cases the former is a preferred embodiment. Based on such understanding, the technical solution of the present invention may be embodied essentially or in a part contributing to the prior art in the form of a software product stored in a storage medium (e.g. ROM/RAM, magnetic disk, optical disk) comprising instructions for causing a terminal (which may be a mobile phone, a computer, a server, an air conditioner, or a network device, etc.) to perform the method according to the embodiments of the present invention.
The embodiments of the present invention have been described above with reference to the accompanying drawings, but the present invention is not limited to the above-described embodiments, which are merely illustrative and not restrictive, and many forms may be made by those having ordinary skill in the art without departing from the spirit of the present invention and the scope of the claims, which are to be protected by the present invention.
Claims (12)
1. A method for calculating a nuclide release activity, comprising:
determination of the steady-state specific activity C of nuclide i in a Loop i (0) The nuclide i is a radionuclide released from the core to the environment;
obtaining a reservoir I of the nuclear species I in the core i The fraction f in the fuel rod cladding gap i And a release time period, and calculates a transient release rate R of the nuclear species i from the core to the primary loop i The R is i And said I i In direct proportion, the R i And f is equal to i Proportional to the ratio;
according to the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t)；
Based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Wherein the time t belongs to the target time period.
2. The method of claim 1, wherein the step of calculating the nuclide release activity is performed based on the formula C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t) comprising:
by the nuclide balance formula in the first loop and the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t), wherein the nuclide balance formula in the one loop comprises:
wherein the R is i A release rate of the nuclear species i from the core to the primary circuit; the lambda is i A decay constant for the nuclide i; the C is i (t) is the transient specific activity of the nuclide i in the loop at time t, C when t=0 i (0) A steady state specific activity for the nuclide i in the one loop; the M is RCS (t) is the coolant charge of the first circuit at time t; and L (t) is the leakage flow rate of the first loop to the second loop at the moment t.
3. The method of claim 1, wherein the nuclide i is an inert gas, and the C-based species is i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Comprising:
acquiring leakage flow L (t) from the first loop to the second loop at the moment t;
the C is subjected to i The product of (t) and L (t) is taken as the release rate Q of the inert gas to the environment at the moment t i (t)；
The Q is set to i (t) performing an integral calculation for a target period of time to obtain the activity Q of the inert gas released to the environment within the target period of time i 。
4. The method of claim 1, wherein the nuclide i is halogen or alkali metal, and the C-based species is i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Comprising:
according to the steady-state specific activity C of the nuclide i in the loop i (0) Calculating the steady-state specific activity A of the nuclide i in the two loops i (0)；
Acquiring leakage parameter information of the first loop to the second loop at the time t, and calculating the leakage parameter information and the C according to the leakage parameter information i (t) and the A i (0) Corresponding to the second loopTransient specific activity A of the nuclide i in the road at the time t i (t)；
Based on the A i (t) calculating the activity Q of the release of the nuclide i to the environment over a target period of time i 。
5. The method of claim 4, wherein the calculating the nuclide release activity is based on the A i (t) calculating the activity Q of the release of the nuclide i to the environment over a target period of time i Comprising:
acquiring a first release parameter of the loop to the environment at the time t, and calculating a second release parameter and the C i (t) the rate Q 'of release of the nuclear species i to the environment at the time t in the corresponding loop' i (t)；
Acquiring a second release parameter of the two loops to the environment at the time t, and calculating the second release parameter and the first release parameter and the A i (t) the rate Q' of release of the nuclear species i to the environment at the time t in the corresponding two loops i (t)；
The Q 'is' i (t) and said Q' i (t) respectively performing integral calculation for a target time period, and taking the sum of the integral calculation as the activity Q of the nuclide i released from the two loops to the environment in the target time period i 。
6. A computing device for nuclide release activity, comprising:
a determination module for determining the steady-state specific activity C of the nuclide i in a loop i (0) The nuclide i is a radionuclide released from the core to the environment;
a first calculation module for obtaining the accumulation amount I of the nuclide I in the reactor core i The fraction f in the fuel rod cladding gap i And a release time period, and calculates a transient release rate R of the nuclear species i from the core to the primary loop i The R is i And said I i In direct proportion, the R i And f is equal to i Proportional to the ratio;
a second calculation module for calculating the difference between the first and second data according to the C i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t)；
A third calculation module for based on the C i (t) calculating the activity Q of the release of the nuclide i to the environment within a target period of time after the rupture of the heat transfer tube i Wherein the time t belongs to the target time period.
7. The apparatus of claim 6, wherein the means for calculating the nuclide release activity,
the second calculation module is used for passing through the nuclide balance formula and the C in the loop i (0) Calculating the R i Transient specific activity C of the nuclide i at time t in the corresponding loop i (t), wherein the nuclide balance formula in the one loop comprises:
wherein the R is i A release rate of the nuclear species i from the core to the primary circuit; the lambda is i A decay constant for the nuclide i; the C is i (t) is the transient specific activity of the nuclide i in the loop at time t, C when t=0 i (0) A steady state specific activity for the nuclide i in the one loop; the M is RCS (t) is the coolant charge of the first circuit at time t; and L (t) is the leakage flow rate of the first loop to the second loop at the moment t.
8. The apparatus of claim 6, wherein the nuclide i is an inert gas and the third calculation module comprises:
the first acquisition submodule is used for acquiring leakage flow L (t) of the first loop to the second loop at the moment t;
a first calculation sub-module for calculating the C i The product of (t) and L (t) is taken as the release rate Q of inert gas to the environment at the moment t i (t)；
A second calculation sub-module for calculating the Q i (t) performing an integral calculation for a target period of time to obtain the activity Q of the inert gas released to the environment within the target period of time i 。
9. The computing device of claim 6, wherein the nuclide i is a halogen or an alkali metal, the third computing module comprising:
a third calculation sub-module for calculating a steady state specific activity C of the nuclide i in the loop i (0) Calculating the steady-state specific activity A of the nuclide i in the two loops i (0)；
A fourth calculation sub-module for obtaining the leakage parameter information of the first loop to the second loop at the time t, and calculating the leakage parameter information and the C according to the leakage parameter information i (t) and the A i (0) Transient specific activity A of the nuclide i at the time t in the corresponding two loops i (t)；
A fifth calculation sub-module for based on the A i (t) calculating the activity Q of the release of the nuclide i to the environment over a target period of time i 。
10. The computing device of claim 9, wherein the fifth computing sub-module comprises:
a first calculation unit for acquiring a first release parameter of the loop to the environment at the time t, and calculating the first release parameter and the C i (t) the rate Q 'of release of the nuclear species i to the environment at the time t in the corresponding loop' i (t)；
A second calculation unit for acquiring a second release parameter of the second loop to the environment at the time t, and calculating the first release parameter and the A i (t) the rate Q' of release of the nuclear species i to the environment at the time t in the corresponding two loops i (t)；
A third calculation unit for calculating the Q' i (t) and said Q' i (t) respectively performing integral calculation for a target time period, and taking the sum of the integral calculation as the activity Q of the nuclide i released from the two loops to the environment in the target time period i 。
11. An electronic device comprising a processor, a memory and a computer program stored on the memory and executable on the processor, the computer program when executed by the processor implementing the steps of the method of calculating the nuclide release activity of any one of claims 1 to 5.
12. A computer readable storage medium, characterized in that it has stored thereon a computer program which, when executed by a processor, implements the steps of the method for calculating the nuclide release activity of any one of claims 1 to 5.
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