CN110110392B - Reactor core parameter calculation method of molten salt reactor with silicon carbide as moderator - Google Patents
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- CN110110392B CN110110392B CN201910309092.4A CN201910309092A CN110110392B CN 110110392 B CN110110392 B CN 110110392B CN 201910309092 A CN201910309092 A CN 201910309092A CN 110110392 B CN110110392 B CN 110110392B
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- 150000003839 salts Chemical class 0.000 title claims abstract description 69
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 title claims abstract description 46
- 229910010271 silicon carbide Inorganic materials 0.000 title claims abstract description 46
- 238000004364 calculation method Methods 0.000 title claims abstract description 33
- 238000000034 method Methods 0.000 claims abstract description 18
- 230000001133 acceleration Effects 0.000 claims abstract description 14
- 230000003111 delayed effect Effects 0.000 claims description 12
- 239000000446 fuel Substances 0.000 claims description 12
- 239000000463 material Substances 0.000 claims description 8
- 230000004992 fission Effects 0.000 claims description 6
- 239000002243 precursor Substances 0.000 claims description 6
- 239000002826 coolant Substances 0.000 claims description 3
- 238000004080 punching Methods 0.000 claims description 3
- 238000001228 spectrum Methods 0.000 claims description 3
- 230000001052 transient effect Effects 0.000 claims description 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 5
- 229910002804 graphite Inorganic materials 0.000 description 5
- 239000010439 graphite Substances 0.000 description 5
- 239000007788 liquid Substances 0.000 description 3
- 230000007547 defect Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 239000012466 permeate Substances 0.000 description 2
- 238000006467 substitution reaction Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000007770 graphite material Substances 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 239000004449 solid propellant Substances 0.000 description 1
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Abstract
The invention discloses a method for calculating reactor core parameters of a molten salt reactor by taking silicon carbide as a moderator, which comprises the following steps: constructing a molten salt pile with silicon carbide as a moderator; constructing a neutron transport model of the molten salt reactor; and calculating the neutron transport model by adopting a graphic processor acceleration technology. The silicon carbide moderated molten salt reactor provided by the invention can enable the silicon carbide moderated molten salt reactor to have higher safety performance. And the calculation method based on the graphic processor acceleration technology can be used for more accurately describing the strong anisotropy condition, and can be used for efficiently obtaining the reactor core physical parameters of the silicon carbide moderated molten salt reactor.
Description
Technical Field
The invention relates to the field of nuclear reactor physical computation, in particular to a method for computing reactor core parameters of a molten salt reactor by taking silicon carbide as a moderator.
Background
The molten salt reactor adopts liquid flowing fuel salt as fuel, has the advantages which are not possessed by a solid fuel nuclear reactor, and avoids the occurrence of fuel melting accidents because the fuel is in a liquid state, thereby leading the molten salt reactor to become the only liquid fuel reactor type in the fourth generation nuclear reactor. However, researches show that high-temperature molten salt is easy to permeate into moderator material graphite adopted by a molten salt reactor, so that local hot spots are formed in the graphite, the local temperature of the graphite in the reactor core of the molten salt reactor can reach 1200 ℃ at most, and finally the breakage rate of the graphite is higher.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provide a method for calculating the reactor core parameters of a molten salt reactor by using silicon carbide as a moderator. The invention adopts silicon carbide material to completely replace graphite material to form a novel molten salt pile with silicon carbide as a moderator. The invention provides a neutron transport dynamics calculation method of the silicon carbide moderated molten salt reactor based on the graphic processor acceleration technology, which can more accurately describe the neutron transport condition with strong anisotropy, so that the calculation result is more consistent with the real condition.
The purpose of the invention can be realized by the following technical scheme:
a method for calculating reactor core parameters of a molten salt reactor by taking silicon carbide as a moderator comprises the following steps:
constructing a molten salt pile with silicon carbide as a moderator;
constructing a neutron transport model of the molten salt reactor;
and calculating the neutron transport model by adopting a graphic processor acceleration technology.
Specifically, the structure of the molten salt pile taking silicon carbide as a moderator is as follows:
the method comprises the steps of punching holes in a columnar silicon carbide material to form a molten salt flow channel and a functional channel, wherein the diameter of the molten salt flow channel is generally 1 cm to 9 cm, the distance between the channels is generally 1.5 cm to 30 cm, and the diameter and the height of the columnar silicon carbide are 100 cm to 400 cm.
The molten salt flow channel flows fuel molten salt which is used as fuel and coolant.
The functional channel is used as a loading channel of a primary neutron source and a secondary neutron source, a moving channel of a control rod, a loading channel of a neutron measuring tube and a temperature measuring instrument, and a placing channel of a material irradiation sample.
Specifically, the neutron fluence rate of the silicon carbide moderated molten salt reactor is solved according to a neutron transport model of the silicon carbide moderated molten salt reactor, and a calculation formula of the neutron transport model is as follows:
wherein v is the neutron velocity,
is a partial derivative operator, phi (r, E, omega, t) is the neutron fluence rate, t is a time variable,
in order to be able to leak the operator,
for transient fission operators, i is the identifier of the slowly-evolving subgroup, χd,iIs the i-th group delayed neutron fission spectrum, pi is the circumference ratio, Ci(r, t) is the concentration of the delayed neutron precursor nucleus,
as a gradient operator, u (r, t) is the molten salt flow velocity, r is the space vector, βiIs the fraction of delayed neutrons in the ith group.
As the calculation amount of the neutron transport model of the silicon carbide moderated molten salt reactor in the formula (1) is large, the transport calculation is accelerated by adopting the graphic processor acceleration technology, so that better calculation efficiency and calculation accuracy are obtained.
Specifically, in the process of calculating the neutron transport kinetic model of the silicon carbide moderated molten salt reactor by adopting the graphic processor acceleration technology, the steady-state critical calculation, the steady-state conjugate neutron transport method and the pre-estimated neutron fluence rate of the silicon carbide moderated molten salt reactor are respectively and sequentially subjected to parallel calculation, and the serial calculation is still adopted for the generation of the shape function, the interpolation of the accurate point reactor parameter, the calculation of the amplitude function, the correction of the neutron fluence rate and the calculation of the delayed neutron precursor nuclear concentration.
Compared with the prior art, the invention has the following beneficial effects:
the silicon carbide moderated molten salt reactor provided by the invention can avoid the defect that molten salt permeates into graphite, so that the silicon carbide moderated molten salt reactor has higher safety performance. And by adopting the neutron transport dynamics calculation method of the silicon carbide moderated molten salt reactor based on the graphic processor acceleration technology, the strong anisotropic condition can be more accurately described, and the reactor core physical parameters of the silicon carbide moderated molten salt reactor can be efficiently obtained.
Drawings
FIG. 1 is a flow chart of a method for calculating core parameters of a molten salt reactor using silicon carbide as a moderator according to the present invention.
FIG. 2 is a flowchart of calculation of a neutron transport dynamics model of a silicon carbide moderated molten salt reactor based on a graphics processor acceleration technique according to an embodiment of the present invention.
Detailed Description
The present invention will be described in further detail with reference to examples and drawings, but the present invention is not limited thereto.
Examples
FIG. 1 is a flow chart of a method for calculating core parameters of a molten salt reactor using silicon carbide as a moderator, comprising the steps of:
constructing a molten salt pile with silicon carbide as a moderator;
constructing a neutron transport model of the molten salt reactor;
and calculating the neutron transport model by adopting a graphic processor acceleration technology.
Specifically, the structure of the molten salt pile taking silicon carbide as a moderator is as follows:
the method comprises the steps of punching holes in a columnar silicon carbide material to form a molten salt flow channel and a functional channel, wherein the diameter of the molten salt flow channel is generally 1 cm to 9 cm, the distance between the channels is generally 1.5 cm to 30 cm, and the diameter and the height of the columnar silicon carbide are 100 cm to 400 cm.
The molten salt flow channel flows fuel molten salt which is used as fuel and coolant.
The functional channel is used as a loading channel of a primary neutron source and a secondary neutron source, a moving channel of a control rod, a loading channel of a neutron measuring tube and a temperature measuring instrument, and a placing channel of a material irradiation sample.
Specifically, the neutron fluence rate of the silicon carbide moderated molten salt reactor is solved according to a neutron transport model of the silicon carbide moderated molten salt reactor, and a calculation formula of the neutron transport model is as follows:
wherein v is the neutron velocity,
is a partial derivative operator, phi (r, E, omega, t) is the neutron fluence rate, t is a time variable,
in order to be able to leak the operator,
for transient fission operators, i is the identifier of the slowly-evolving subgroup, χd,iIs the i-th group delayed neutron fission spectrum, pi is the circumference ratio, Ci(r, t) is the concentration of the delayed neutron precursor nucleus,
as a gradient operator, u (r, t) is the molten salt flow velocity, r is the space vector, βiIs the fraction of delayed neutrons in the ith group.
As the calculation amount of the neutron transport model of the silicon carbide moderated molten salt reactor in the formula (1) is large, the transport calculation is accelerated by adopting the graphic processor acceleration technology, so that better calculation efficiency and calculation accuracy are obtained.
As shown in fig. 2, a flow chart for calculating a neutron transport dynamics model of a silicon carbide moderated molten salt reactor by using a graph processor acceleration technology is provided, which specifically comprises the following steps: and respectively and sequentially carrying out parallel calculation on the steady-state critical calculation, the steady-state conjugate neutron transport method and the pre-estimated neutron fluence rate of the silicon carbide moderated molten salt reactor, and still adopting serial calculation for the generation of a shape function, the interpolation of an accurate point reactor parameter, the calculation of an amplitude function, the correction of the neutron fluence rate and the calculation of the delayed neutron precursor nucleus concentration.
In the above-described acceleration using a graphics processor, there are at least six active thread bundles per streaming multiprocessor in order to hide latency, and in order to avoid idle execution units, the thread bundles cannot all come from one thread block, so there are preferably more than two active thread blocks per streaming multiprocessor. Smaller thread blocks use less resources and there may be more active thread blocks on a streaming multiprocessor and more threads in larger thread blocks may communicate. Furthermore, in order to efficiently utilize the execution units, the number of threads per thread block is preferably an integer multiple of 32.
The above embodiments are preferred embodiments of the present invention, but the present invention is not limited to the above embodiments, and any other changes, modifications, substitutions, combinations, and simplifications which do not depart from the spirit and principle of the present invention should be construed as equivalents thereof, and all such changes, modifications, substitutions, combinations, and simplifications are intended to be included in the scope of the present invention.
Claims (4)
1. A method for calculating reactor core parameters of a molten salt reactor by taking silicon carbide as a moderator is characterized by comprising the following steps of:
the method comprises the following steps of constructing a molten salt pile taking silicon carbide as a moderator, wherein the structure is as follows: punching holes in the columnar silicon carbide material to form a molten salt flow channel and a functional channel, wherein the diameter of the molten salt flow channel ranges from 1 cm to 9 cm, the distance between the molten salt flow channel and the molten salt flow channel ranges from 1.5 cm to 30 cm, and the diameter and the height of the columnar silicon carbide respectively range from 100 cm to 400 cm;
fuel molten salt flows in the molten salt flow channel, and the fuel molten salt is used as fuel and coolant;
the functional channel is used as a loading channel of a primary neutron source and a secondary neutron source, a moving channel of a control rod, a loading channel of a neutron measuring tube and a temperature measuring instrument, and a placing channel of a material irradiation sample;
constructing a neutron transport model of the molten salt reactor;
and calculating the neutron transport model by adopting a graphic processor acceleration technology.
2. The method for calculating the reactor core parameters of the molten salt reactor taking the silicon carbide as the moderator according to claim 1, wherein the calculation formula of the neutron transport model of the molten salt reactor is as follows:
wherein v is the neutron velocity,
is a partial derivative operator, phi (r, E, omega, t) is the neutron fluence rate, t is a time variable,
in order to be able to leak the operator,
for transient fission operators, i is the identifier of the slowly-evolving subgroup, χd,iIs the i-th group delayed neutron fission spectrum, pi is the circumference ratio, Ci(r, t) is the concentration of delayed neutron precursor nucleus, (. DELTA.) is a gradient operator, u (r, t) is the molten salt flow velocity, r is a space vector, betaiIs the fraction of delayed neutrons in the ith group.
3. The method for calculating the reactor core parameters of the molten salt reactor taking the silicon carbide as the moderator according to claim 1, wherein in the process of calculating the neutron transport model of the silicon carbide moderated molten salt reactor by adopting the graphic processor acceleration technology, the steady-state criticality, the neutron transport model and the neutron fluence rate of the silicon carbide moderated molten salt reactor are calculated in parallel, and the generation of the shape function, the interpolation calculation of the precise point reactor parameters, the calculation of the amplitude function, the correction of the neutron fluence rate and the calculation of the delayed neutron precursor nuclear concentration adopt serial calculation.
4. The method of claim 3, wherein during the accelerated calculation using the graphics processor, there are at least six active thread bundles on each stream multiprocessor, the thread bundles cannot all come from one thread block, and the number of threads in each thread block needs to be an integral multiple of 32.
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