Operation Management Method and System for the Cooling System of Spent Fuel Pool

Abstract

The present invention relates to a method and system for commissioning management of a spent fuel pool cooling system. The method for commissioning management of the cooling system includes: obtaining the three-part decay heat power per unit mass of metallic uranium for each group of spent fuel assemblies; obtaining the mass of each group of spent fuel assemblies and calculating the total decay heat power of the spent fuel pool by using a VBA tool; obtaining a pre-established heat exchange model of the spent fuel pool and determining the inlet temperature limit of the cooling water of the currently commissioned cooling system according to the heat exchange model of the spent fuel pool and the total decay heat power of the spent fuel pool; measuring the inlet temperature of the cooling water of the currently commissioned cooling system to obtain an inlet temperature measurement value, and determining a commissioning plan for the cooling system according to the inlet temperature measurement value and the inlet temperature limit. Implementing the technical solution of the present invention can not only save manpower and time, but also provide scientific opinions on the commissioning of the cooling system for operators.

Description

Technical Field

[0001] The present invention relates to the field of nuclear power, and particularly to a method and system for commissioning management of a cooling system for a spent fuel pool. Background Art

[0002] Metal uranium fuel assemblies undergo continuous spontaneous chain nuclear fission reactions in a nuclear reactor. After a certain period of fission, a large amount of fissile nuclide metal uranium is consumed, and a large amount of fission products and actinide nuclides are generated. After the core of the nuclear reactor stops operating, the fission products and actinide nuclides contain a large amount of radioactivity and will continuously decay and release a large amount of heat.

[0003] Currently, existing decay heat calculation software can only calculate the decay heat power of three parts (light elements, actinides, fission products) per unit mass of metal uranium. Then, a large amount of manpower still needs to be spent on repeated superposition calculations of the decay heat power to obtain the total decay heat of the spent fuel pool. Moreover, the existing technology cannot give suggestions on the commissioning of the cooling system based on the temperature of the spent fuel pool and the total decay heat of the spent fuel pool. Therefore, the deficiencies of the existing technology are summarized as follows:

[0004] 1. A large amount of manpower needs to be spent on classifying, screening, calculating, and statistically calculating each group of fuel assemblies to obtain the decay heat data of each group of fuel assemblies. The calculation amount is large and cannot respond in a timely manner according to on-site requirements;

[0005] 2. The relationship between the decay heat of the spent fuel pool and the cooling water temperature cannot be determined, and thus the commissioning opinion of the cooling system cannot be provided to the operators. Summary of the Invention

[0006] The technical problem to be solved by the present invention is to provide a method and system for commissioning management of a cooling system to address the above-mentioned defects of the existing technology, such as wasting manpower and time and being unable to provide the commissioning opinion of the cooling system to the operators.

[0007] The technical solution adopted by the present invention to solve its technical problem is to construct a method for commissioning management of a cooling system for a spent fuel pool, including:

[0008] Step S10. Obtain the decay heat power of three parts per unit mass of metal uranium for each group of spent fuel assemblies in the spent fuel pool according to the power history of each group of spent fuel assemblies;

[0009] Step S20. Obtain the mass of each group of spent fuel assemblies, and calculate the total decay heat power of the spent fuel pool by using the VBA tool according to the mass of each group of spent fuel assemblies and the decay heat power of three parts per unit mass of metal uranium for each group of spent fuel assemblies;

[0010] Step S30. Obtain the pre-established spent fuel pool heat exchange model, and determine the inlet temperature limit of the cooling water of the currently operating cooling system according to the spent fuel pool heat exchange model and the total decay heat power of the spent fuel pool, where the spent fuel pool heat exchange model is related to the preset temperature alarm threshold of the spent fuel pool, the cooling water flow rate of the cooling system, the flow rate of the boric acid-containing water in the spent fuel pool, and the current configuration of the cooling system;

[0011] Step S40. Measure the inlet temperature of the cooling water of the currently operating cooling system to obtain an inlet temperature measurement value, and determine the operation plan of the cooling system according to the inlet temperature measurement value and the inlet temperature limit.

[0012] Preferably, the step S20 includes:

[0013] Step S21. Obtain the mass of each group of spent fuel assemblies, and calculate the decay heat power of each group of spent fuel assemblies according to the mass of each group of spent fuel assemblies and the three-part decay heat power of the unit mass of metallic uranium in each group of spent fuel assemblies;

[0014] Step S22. Superimpose the decay heat power of each group of spent fuel assemblies to obtain the total decay heat power of the spent fuel pool.

[0015] Preferably, in the step S21, the decay heat power of each group of spent fuel assemblies is calculated according to Formula 1:

[0016] Q i =(Q1 + Q2 + Q3)*m i Formula 1

[0017] where Q i is the decay heat power of the i-th group of spent fuel assemblies, Q1, Q2, and Q3 are the three-part decay heat powers of the unit mass of metallic uranium in the i-th group of spent fuel assemblies respectively, and m i is the mass of the i-th group of spent fuel assemblies.

[0018] Preferably, in the step S22, the total decay heat power of the spent fuel pool is calculated according to Formula 2:

[0019]

[0020] where Q is the total decay heat power of the spent fuel pool, and n is the number of spent fuel assemblies in the spent fuel pool.

[0021] Preferably, the step S20 further includes:

[0022] Step S23. Output the decay heat power of each group of spent fuel assemblies and the total decay heat power of the spent fuel pool.

[0023] Preferably, after the step S20, it further includes:

[0024] Step S40. Calculate the temperature rise rate of the boron-containing water in the spent fuel pool according to the total decay heat power of the spent fuel pool, the volume of the spent fuel pool, the volume of each group of spent fuel assemblies in the spent fuel pool, the number of spent fuel assemblies in the spent fuel pool, and the specific heat capacity of the boron-containing water in the spent fuel pool.

[0025] Preferably, in step S40, calculate the temperature rise rate of the boron-containing water in the spent fuel pool according to formula 3:

[0026]

[0027] Wherein, is the temperature rise rate of the boron-containing water in the spent fuel pool, Q is the total decay heat power of the spent fuel pool, C2 is the specific heat capacity of the boron-containing water in the spent fuel pool, V is the volume of the spent fuel pool, V m is the volume of each group of spent fuel assemblies in the spent fuel pool, and n is the number of spent fuel assemblies in the spent fuel pool.

[0028] Preferably, the spent fuel pool heat exchange model is:

[0029]

[0030]

[0031] Wherein, T A is the inlet temperature limit value of the cooling water of the currently operating cooling system, t A is the temperature alarm threshold of the spent fuel pool, Q is the total decay heat power of the spent fuel pool, W1 is the cooling water flow rate of the currently operating cooling system, W2 is the flow rate of the boron-containing water in the spent fuel pool, C1 is the specific heat capacity of the cooling water, C2 is the specific heat capacity of the boron-containing water in the spent fuel pool, K is the heat transfer coefficient of the plate heat exchanger of the cooling system, S is the heat exchange area of the plate heat exchanger of the cooling system, and q is the number of columns of the currently operating cooling system.

[0032] Preferably, in step S40, determine the operation plan of the cooling system according to the inlet temperature measurement value and the inlet temperature limit value, including:

[0033] Step S41. If the inlet temperature measurement value is less than the inlet temperature limit value, maintain the number of columns of the currently operating cooling system;

[0034] Step S42. If the inlet temperature measurement value is not less than the inlet temperature limit value, add one column of the operating cooling system.

[0035] The present invention also constructs an operation management system for the cooling system of a spent fuel pool, which includes a processor and a memory storing a computer program. When the processor executes the computer program, the steps of the operation management method for the cooling system of the spent fuel pool described in any one of the above are implemented.

[0036] For the technical solution provided by the present invention, the VBA tool can automatically obtain the decay heat powers of three parts of unit mass of metallic uranium from the original decay heat calculation software and automatically calculate the total decay heat power of the spent fuel pool. Therefore, the total decay heat power of the spent fuel pool can be obtained in one key, saving a large amount of manpower and time. Moreover, during normal operation conditions, based on the calculated total decay heat power of the spent fuel pool and the pre-established heat exchange model of the spent fuel pool, the inlet temperature limit of the cooling water of the currently operating cooling system can be automatically determined, and by comparing the inlet temperature limit with the measured value of the inlet temperature of the cooling water of the currently operating cooling system, the operation plan of the cooling system can be determined, providing scientific opinions for the operation personnel on the operation of the heat exchanger heat exchange system. Brief Description of the Drawings

[0037] In order to more clearly illustrate the embodiments of the present invention, the drawings required for the description of the embodiments will be briefly introduced below. Obviously, the drawings in the following description are only some embodiments of the present invention. For those of ordinary skill in the art, without creative efforts, other drawings can be obtained based on these drawings. In the drawings:

[0038] Figure 1 It is a flowchart of the first embodiment of the method for determining the cooling water temperature of the spent fuel pool of the present invention. Detailed Embodiments

[0039] Next, the technical solutions in the embodiments of the present invention will be clearly and completely described in conjunction with the drawings in the embodiments of the present invention. Obviously, the described embodiments are only a part of the embodiments of the present invention, rather than all the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those of ordinary skill in the art without creative efforts belong to the scope of protection of the present invention.

[0040] First of all, it should be noted that the original decay heat calculation software can only calculate the decay heat of unit mass of metallic uranium after core fission. However, the spent fuel pool contains a large number of spent fuel assemblies, and the metallic uranium loading of each spent fuel assembly is different. To calculate the total decay heat of the spent fuel pool, a large amount of manual superposition operations need to be performed on the output file of the original decay heat calculation software, which thus consumes a great deal of manpower and time, and there are also many human errors. In addition, when the spent fuel assemblies are stored in the spent fuel pool, the decay heat of the spent fuel pool needs to be discharged into the ultimate heat sink by using the heat exchange principle. Therefore, the spent fuel pool must be equipped with a cooling system (each column of the cooling system includes 1 circulating pump and 1 heat exchanger). However, if the number of columns of the cooling system put into operation is too small, the decay heat of the spent fuel pool cannot be exported; if the number of columns of the cooling system put into operation is too large, it is not optimal in terms of economic benefits. Therefore, the spent fuel pool needs to be equipped with a cooling system with an appropriate number of columns.

[0041] Figure 1 FIG. 4 is a flowchart of the first embodiment of the method for determining the cooling water temperature of the spent fuel pool of the present invention. The method for determining the cooling water temperature of the spent fuel pool in this embodiment includes the following steps:

[0042] Step S10. Obtain the three-part decay heat power of unit mass of metallic uranium for each group of spent fuel assemblies in the spent fuel pool according to the power history of each group of spent fuel assemblies.

[0043] In this step, the original decay heat calculation software can be used to obtain the three-part (light elements, actinides, fission products) decay heat power of unit mass of metallic uranium. Specifically, input the power history of each group of spent fuel assemblies in the spent fuel pool into the original decay heat calculation software, and then the three-part decay heat power of unit mass of metallic uranium for each group of spent fuel assemblies can be obtained through the OUT file output by this decay heat calculation software.

[0044] Step S20. Obtain the mass of each group of spent fuel assemblies, and calculate the total decay heat power of the spent fuel pool by using the VBA tool according to the mass of each group of spent fuel assemblies and the three-part decay heat power of unit mass of metallic uranium for each group of spent fuel assemblies.

[0045] In this step, the VBA tool is used to superimpose the three-part decay heat power data of unit mass of metallic uranium obtained from the original decay heat calculation software, and then calculate the total decay heat power of the spent fuel pool according to the metallic uranium loading of each group of spent fuel assemblies.

[0046] Step S30. Obtain the pre-established spent fuel pool heat exchange model, and determine the inlet temperature limit of the cooling water of the currently operating cooling system according to the spent fuel pool heat exchange model and the total decay heat power of the spent fuel pool, where the spent fuel pool heat exchange model is related to the preset temperature alarm threshold of the spent fuel pool, the cooling water flow rate of the cooling system, the flow rate of the boron-containing water in the spent fuel pool, and the current configuration of the cooling system;

[0047] Step S40. Measure the inlet temperature of the cooling water of the currently operating cooling system to obtain the inlet temperature measurement value, and determine the operation plan of the cooling system according to the inlet temperature measurement value and the inlet temperature limit.

[0048] In the technical solution of this embodiment, the VBA tool can automatically obtain the three-part decay heat power of unit mass of metallic uranium from the original decay heat calculation software and automatically calculate the total decay heat power of the spent fuel pool. Therefore, the total decay heat power of the spent fuel pool can be obtained in one key, saving a large amount of manpower and time. Moreover, during normal operating conditions, according to the calculated total decay heat power of the spent fuel pool and the pre-established spent fuel pool heat exchange model, the inlet temperature limit of the cooling water of the currently operating cooling system can be automatically determined, and by comparing the inlet temperature limit with the measured value of the inlet temperature of the cooling water of the currently operating cooling system, the operation plan of the cooling system can be determined, providing scientific opinions for the operation personnel on the operation of the heat exchanger heat exchange system.

[0049] Further, in an alternative embodiment, step S20 includes:

[0050] Step S21. Obtain the mass of each group of spent fuel assemblies, and calculate the decay heat power of each group of spent fuel assemblies according to the mass of each group of spent fuel assemblies and the three-part decay heat power of unit mass of metallic uranium in each group of spent fuel assemblies. Specifically, the decay heat power of each group of spent fuel assemblies can be calculated according to formula 1:

[0051] Q i =(Q1 + Q2 + Q3)*m i Formula 1

[0052] Where Q i is the decay heat power of the i-th group of spent fuel assemblies, Q1, Q2, and Q3 are the three-part decay heat powers of unit mass of metallic uranium in the i-th group of spent fuel assemblies respectively, and m i is the mass of the i-th group of spent fuel assemblies;

[0053] Step S22. Superimpose the decay heat powers of each group of spent fuel assemblies to obtain the total decay heat power of the spent fuel pool. Specifically, the total decay heat power of the spent fuel pool is calculated according to formula 2:

[0054]

[0055] Among them, Q is the total decay heat power of the spent fuel pool, and n is the number of spent fuel assemblies in the spent fuel pool.

[0056] Furthermore, in an alternative embodiment, step S20 further includes:

[0057] Step S23. Output the decay heat power of each group of spent fuel assemblies and the total decay heat power of the spent fuel pool. For example, the decay heat power of each group of spent fuel assemblies and the total decay heat power of the spent fuel pool can be output in the form of graphs or tables.

[0058] Furthermore, based on the experience feedback from the Fukushima nuclear accident in 2011, in a severe accident, if the spent fuel pool loses cooling, the temperature of the spent fuel assemblies stored in the spent fuel pool rises, resulting in the breakage of the spent fuel assemblies and the release of a large amount of radioactive substances. Therefore, the power plant must have the ability to quickly calculate the decay heat of the spent fuel pool to provide reference for the operating personnel and the emergency organization. Based on this, in an alternative embodiment, after step S20, it further includes:

[0059] Step S40. Calculate the temperature rise rate of the boron water in the spent fuel pool according to the total decay heat power of the spent fuel pool, the volume of the spent fuel pool, the volume of each group of spent fuel assemblies in the spent fuel pool, the number of spent fuel assemblies in the spent fuel pool, and the specific heat capacity of the boron water in the spent fuel pool. Specifically, calculate the temperature rise rate of the boron water in the spent fuel pool according to formula 3:

[0060]

[0061] Among them, is the temperature rise rate of the boron water in the spent fuel pool, Q is the total decay heat power of the spent fuel pool, C2 is the specific heat capacity of the boron water in the spent fuel pool, V is the volume of the spent fuel pool, V m is the volume of each group of spent fuel assemblies in the spent fuel pool, and n is the number of spent fuel assemblies in the spent fuel pool.

[0062] In this embodiment, according to the boron water loading amount in the spent fuel pool after storing n groups of spent fuel assemblies, the temperature rise rate of the spent fuel pool when active cooling is lost can be obtained, providing a reference for the operating personnel and the emergency organization to accurately judge.

[0063] Furthermore, in an alternative embodiment, the heat exchange model of the spent fuel pool is:

[0064]

[0065]

[0066] Wherein, TA is the inlet temperature limit value of the cooling water of the currently operating cooling system, tA is the temperature alarm threshold of the spent fuel pool, Q is the total decay heat power of the spent fuel pool, W1 is the cooling water flow rate of the currently operating cooling system, W2 is the flow rate of the boron-containing water in the spent fuel pool, C1 is the specific heat capacity of the cooling water, C2 is the specific heat capacity of the boron-containing water in the spent fuel pool, K is the heat transfer coefficient of the plate heat exchanger of the cooling system, S is the heat transfer area of the plate heat exchanger of the cooling system, and q is the number of columns of the currently operating cooling system.

[0067] Moreover, in step S40, according to the measured inlet temperature value and the inlet temperature limit value, determine the operation plan of the cooling system, including:

[0068] Step S41. If the measured inlet temperature value is less than the inlet temperature limit value, maintain the number of columns of the currently operating cooling system;

[0069] Step S42. If the measured inlet temperature value is not less than the inlet temperature limit value, add one more column of the cooling system to be put into operation.

[0070] Regarding the heat exchange model of the spent fuel pool, it should be noted that generally, the spent fuel pool is equipped with 3 columns of cooling systems, each column of the cooling system is equipped with 1 circulating pump and 1 heat exchanger, and the heat exchanger is a plate heat exchanger. The following takes the currently operating one column of cooling system as an example to illustrate the establishment process of the heat exchange model of the spent fuel pool:

[0071] 1. Calculate the unknown parameter K*S:

[0072] When the heat exchanger is a countercurrent plate heat exchanger, according to the design values of Q1, T in 、T out 、t in 、t out ,use formula 2-1 to calculate K*S:

[0073]

[0074] In the formula: K is the heat transfer coefficient of the heat exchanger; S is the heat transfer area of the heat exchanger; Q1 is the total decay heat power of the spent fuel pool; T in is the inlet temperature of the cooling water; T out is the outlet temperature of the cooling water; t in is the inlet temperature of the boron-containing water in the spent fuel pool; t out is the outlet temperature of the boron-containing water in the spent fuel pool, and the design values of Q1, T in 、T out 、t in 、t out can be obtained by querying the design specification of the heat exchanger.

[0075] 2. Calculate the unknown parameter θ1:

[0076] According to the principle of heat balance, the heat taken away by the cooling system is the same as the heat released by the boron-containing water in the spent fuel pool, and their heat exchange relationship is:

[0077] Q1 = C1W1(t in -t out ) = C2W2(T out -T in ) Equation 2-2

[0078] Where: Q1 is the heat absorbed by the cooling system / the heat released by the boron-containing water in the spent fuel pool; C1 is the specific heat capacity of the boron-containing water in the spent fuel pool (obtainable from the thermohydraulic diagram); W1 is the flow rate of the boron-containing water in the spent fuel pool; C2 is the specific heat capacity of the cooling water in the cooling system (obtainable from the thermohydraulic diagram); W2 is the flow rate of the cooling water in the cooling system. Q1, W1, and W2 are obtained from the design specification.

[0079] Combining Equation 2-1 and Equation 2-2, we can get:

[0080]

[0081] Among them, the flow rate W1 of the boron-containing water in the spent fuel pool and the flow rate W2 of the cooling water in the cooling system can be obtained through the design specification; the specific heat capacity C1 of the boron-containing water in the spent fuel pool and the specific heat capacity C2 of the cooling water in the cooling system can be obtained by looking up the table; θ1 is an intermediate variable parameter.

[0082] 3. Obtain the relationship between the total decay heat power Q of the spent fuel pool and the inlet temperature limit T A of the cooling water in the spent fuel pool cooling system:

[0083] Transform Equation 2-3 into:

[0084]

[0085] Substitute the total decay heat power Q of the spent fuel pool (which is a function of the time when the spent fuel assembly stops fission) and the temperature alarm threshold t in corresponding to the inlet temperature t A of the boron-containing water in the spent fuel pool (which can be set to 50 °C to ensure the safety of the spent fuel pool) into Equation 2-4. At this time, Equation 2-4 is transformed into the relationship between the total decay heat power Q of the spent fuel pool and the inlet temperature limit T in corresponding to the inlet temperature T A of the cooling water in the currently operating cooling system of the spent fuel pool, that is, determine the relationship between the currently operating cooling system that can derive the total decay heat power Q and the required maximum spent fuel pool cooling water temperature (the inlet temperature limit T A ):

[0086]

[0087] After obtaining the inlet temperature limit value T of the cooling water of the currently operating cooling system A it is possible to determine the operation plan of the cooling system in combination with the measured value T2 of the inlet temperature of the cooling water of the currently operating cooling system. For example, if T2 (measured in real time on site) is less than T A , it indicates that the heat can be dissipated by the currently operating one row of cooling systems, and the number of operating rows can be maintained unchanged; conversely, if T2 (measured in real time on site) is not less than T A , it indicates that the heat cannot be dissipated by the currently operating one row of cooling systems, and two rows of cooling systems need to be put into operation. As time goes by, the total decay heat power Q of the spent fuel pool decreases monotonically, and the trend gradually slows down, which can provide the shortest time for two rows of cooling systems to be put into operation.

[0088] Similarly, if two rows of cooling systems are currently operating and the two rows of cooling systems are in parallel, and each row of cooling systems is equipped with one circulation pump and one heat exchanger, the establishment process of the heat exchange model of the spent fuel pool is as follows:

[0089] Formula 2-1 can be transformed into:

[0090]

[0091] Formula 2-2 can be transformed into:

[0092] Q2 = 2C1W1(t in -t out ) = 2C2W2(T out -T in ) Formula 2-7

[0093] Combining Formula 2-6 and Formula 2-7, we can get:

[0094]

[0095]

[0096] Similarly, Formula 2-8 can be transformed into:

[0097]

[0098] Substitute the total decay heat power Q of the spent fuel pool (which is a function of the time when the spent fuel assembly stops fission) and the boron water inlet temperature t of the spent fuel pool in corresponding temperature alarm threshold t A (which can be set to 50 °C to ensure the safety of the spent fuel pool) obtained from the previous calculation into Formula 2-9. At this time, Formula 2-9 is transformed into the total decay heat power Q of the spent fuel pool and the inlet temperature T of the cooling water of the currently operating cooling system of the spent fuel poolin The corresponding inlet temperature limit T A relationship, that is, to determine the relationship between the total decay heat power Q that can be exported by the currently operating cooling system and the required maximum cooling water temperature of the spent fuel pool (the inlet temperature limit T of the cooling water A ):

[0099]

[0100] After obtaining the inlet temperature limit T of the cooling water of the currently operating cooling system A , the operation plan of the cooling system can be determined by combining it with the measured value T2 of the inlet temperature of the cooling water of the currently operating cooling system. For example, if T2 (measured in real time on site) is less than T A , it indicates that the currently operating two columns of cooling systems can export heat, and the current number of operating columns can be maintained; on the contrary, if T2 (measured in real time on site) is not less than T A , it indicates that the currently operating two columns of cooling systems cannot export heat, and three columns of cooling systems need to be put into operation. As time goes by, the total decay heat power Q of the spent fuel pool decreases monotonically, and the trend gradually slows down, which can provide the shortest time for three columns of cooling systems to be put into operation.

[0101] According to the above derivation process, if q columns of cooling systems are currently in operation, and the q columns of cooling systems are in parallel, and each column of cooling system is equipped with 1 circulating pump and 1 heat exchanger, the establishment process of the heat exchange model of the spent fuel pool is as follows:

[0102] Formula 2-1 can be transformed into:

[0103]

[0104] Formula 2-2 can be transformed into:

[0105] Q2 = qC1W1(t in - t out ) = qC2W2(T out - T in ) Formula 2-12

[0106] Combining Formula 2-11 and Formula 2-12, we can get:

[0107]

[0108]

[0109] Similarly, Formula 2-13 can be transformed into:

[0110]

[0111] The total decay heat power Q of the spent fuel pool obtained from the previous calculation (which is a function of the time when the fission of the spent fuel assembly stops) and the inlet temperature t of the borated water in the spent fuel pool in The corresponding temperature alarm threshold t A (which can be set to 50 °C to ensure the safety of the spent fuel pool) is substituted into Equation 2-14. At this time, Equation 2-14 is transformed into the relationship between the total decay heat power Q of the spent fuel pool and the inlet temperature limit TA of the cooling water of the currently operating cooling system in the spent fuel pool, that is, to determine the relationship between the total decay heat power Q that can be removed by the currently operating cooling system and the highest required cooling water temperature (the inlet temperature limit TA of the cooling water) of the spent fuel pool:

[0112]

[0113] After obtaining the inlet temperature limit TA of the cooling water of the currently operating cooling system, the operation plan of the cooling system can be determined by combining the measured value T2 of the inlet temperature of the cooling water of the currently operating cooling system. For example, if T2 (measured in real time on site) is less than TA, it indicates that the currently operating q-column cooling system can remove heat, and the current number of operating columns can be maintained; conversely, if T2 (measured in real time on site) is not less than TA, it indicates that the currently operating q-column cooling system cannot remove heat, and one more column of the cooling system needs to be put into operation.

[0114] The above are only the preferred embodiments of the present invention and are not used to limit the present invention. For those skilled in the art, the present invention can have various changes and modifications. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present invention shall be included within the scope of the claims of the present invention.

Claims

1. A method for commissioning management of a spent fuel pool cooling system, characterized in that Including: Step S10. Obtain the three - part decay heat power per unit mass of metallic uranium for each group of spent fuel assemblies in the spent fuel pool according to the power history of each group of spent fuel assemblies. Step S20. Obtain the mass of each group of spent fuel assemblies, and calculate the total decay heat power of the spent fuel pool by using the VBA tool according to the mass of each group of spent fuel assemblies and the three - part decay heat power per unit mass of metallic uranium for each group of spent fuel assemblies. Step S30. Obtain the pre - established heat exchange model of the spent fuel pool, and determine the inlet temperature limit of the cooling water of the currently operating cooling system according to the heat exchange model of the spent fuel pool and the total decay heat power of the spent fuel pool, wherein the heat exchange model of the spent fuel pool is related to the preset temperature alarm threshold of the spent fuel pool, the cooling water flow rate of the cooling system, the flow rate of the boron - containing water in the spent fuel pool, and the current configuration of the cooling system. Step S40. Measure the inlet temperature of the cooling water of the currently operating cooling system to obtain the inlet temperature measurement value, and determine the operation plan of the cooling system according to the inlet temperature measurement value and the inlet temperature limit. The heat exchange model of the spent fuel pool is: Among them, T A is the inlet temperature limit value of the cooling water of the currently operating cooling system, t A is the temperature alarm threshold of the spent fuel pool, Q is the total decay heat power of the spent fuel pool, W1 is the cooling water flow rate of the currently operating cooling system, W2 is the flow rate of the boron-containing water in the spent fuel pool, C1 is the specific heat capacity of the cooling water, C2 is the specific heat capacity of the boron-containing water in the spent fuel pool, K is the heat transfer coefficient of the plate heat exchanger of the cooling system, S is the heat transfer area of the plate heat exchanger of the cooling system, and q is the number of columns of the currently operating cooling system.

2. The commissioning management method for the cooling system of the spent fuel pool according to claim 1, wherein The step S20 includes: Step S21. Obtain the mass of each group of spent fuel assemblies, and calculate the decay heat power of each group of spent fuel assemblies according to the mass of each group of spent fuel assemblies and the three - part decay heat power per unit mass of metallic uranium for each group of spent fuel assemblies. Step S22. Superimpose the decay heat powers of each group of spent fuel assemblies to obtain the total decay heat power of the spent fuel pool.

3. The method for commissioning management of the cooling system of the spent fuel pool according to claim 2, wherein In the step S21, calculate the decay heat power of each group of spent fuel assemblies according to formula 1: Formula 1 Among them, Q i is the decay heat power of the i-th group of spent fuel assemblies, and Q1, Q2, and Q3 are the decay heat powers of three parts per unit mass of metallic uranium in the i-th group of spent fuel assemblies, respectively. m i is the mass of the i-th group of spent fuel assemblies.

4. The method for commissioning management of the cooling system of the spent fuel pool according to claim 3, wherein In the step S22, calculate the total decay heat power of the spent fuel pool according to formula 2: Formula 2 Wherein, Q is the total decay heat power of the spent fuel pool, and n is the number of spent fuel assemblies in the spent fuel pool.

5. The operation management method of the cooling system of the spent fuel pool according to claim 2, characterized in that, The step S20 further includes: Step S23. Output the decay heat power of each group of spent fuel assemblies and the total decay heat power of the spent fuel pool.

6. The method for commissioning management of the cooling system of a spent fuel pool according to claim 1, characterized in that, After the step S20, it further includes: Step S40. Calculate the temperature rise rate of the boron - containing water in the spent fuel pool according to the total decay heat power of the spent fuel pool, the volume of the spent fuel pool, the volume of each group of spent fuel assemblies in the spent fuel pool, the number of spent fuel assemblies in the spent fuel pool, and the specific heat capacity of the boron - containing water in the spent fuel pool.

7. The method for commissioning management of the cooling system of a spent fuel pool according to claim 6, wherein, In the step S40, calculate the temperature rise rate of the boron - containing water in the spent fuel pool according to formula 3: Formula 3 Among them, is the temperature rise rate of the boron water in the spent fuel pool, Q is the total decay heat power of the spent fuel pool, C2 is the specific heat capacity of the boron-containing water in the spent fuel pool, V is the volume of the spent fuel pool, and V m is the volume of each spent fuel assembly in the spent fuel pool, and n is the number of spent fuel assemblies in the spent fuel pool.

8. The method for commissioning management of the cooling system of a spent fuel pool according to claim 1, wherein In the step S40, determining the operation plan of the cooling system according to the inlet temperature measurement value and the inlet temperature limit includes: Step S41. If the inlet temperature measurement value is less than the inlet temperature limit, maintain the number of columns of the currently operating cooling system. Step S42. If the inlet temperature measurement value is not less than the inlet temperature limit, add one more column of the cooling system in operation.

9. A commissioning management system for the cooling system of a spent fuel pool, comprising a processor and a memory storing a computer program, characterized in that, When the processor executes the computer program, it implements the steps of the method for managing the operation of the cooling system of the spent fuel pool according to any one of claims 1 - 8.

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