CN104021278A - Calculation method for non-fuel burnable poison burn-up in reactor - Google Patents
Calculation method for non-fuel burnable poison burn-up in reactor Download PDFInfo
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- 239000000446 fuel Substances 0.000 title claims abstract description 55
- 238000004364 calculation method Methods 0.000 title claims abstract description 51
- 239000002574 poison Substances 0.000 title claims abstract description 26
- 231100000614 poison Toxicity 0.000 title claims abstract description 26
- 230000004907 flux Effects 0.000 claims abstract description 56
- 238000000034 method Methods 0.000 claims abstract description 16
- 230000004992 fission Effects 0.000 claims description 21
- 231100000331 toxic Toxicity 0.000 claims description 4
- 230000002588 toxic effect Effects 0.000 claims description 4
- 238000012935 Averaging Methods 0.000 claims description 3
- 229910052768 actinide Inorganic materials 0.000 claims description 3
- 150000001255 actinides Chemical class 0.000 claims description 3
- 238000000342 Monte Carlo simulation Methods 0.000 abstract description 7
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 description 7
- 229910052776 Thorium Inorganic materials 0.000 description 7
- 229910007948 ZrB2 Inorganic materials 0.000 description 3
- 238000012937 correction Methods 0.000 description 3
- 239000011248 coating agent Substances 0.000 description 2
- 238000000576 coating method Methods 0.000 description 2
- 238000002485 combustion reaction Methods 0.000 description 2
- 238000005192 partition Methods 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- VWZIXVXBCBBRGP-UHFFFAOYSA-N boron;zirconium Chemical compound B#[Zr]#B VWZIXVXBCBBRGP-UHFFFAOYSA-N 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 239000006185 dispersion Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000012528 membrane Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
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Abstract
The invention discloses a calculation method for non-fuel burnable poison burn-up in a reactor. The calculation method includes the steps that (a), total power is input for burn-up calculation in the reactor; (b), power and flux of all burn-up regions are distributed; (c), constant power burn-up calculation is adopted for a fuel region, and constant-flux burn-up calculation is adopted for a non-fuel burnable poison region. The mixed burn-up calculation mode based on the Monte Carlo method is adopted; for the fuel region, the constant power mode is adopted for burn-up; for the ultra-low power regions of non-fuel burnable poison, thorium-base fuel and others, the constant-flux mode is adopted for burn-up. The application range of burn-up calculation based on the Monte Carlo method is enlarged, and the method can be used for performing processing including burning calculation on the ultra-low power regions of the non-fuel burnable poison, the thorium-base fuel and others. The calculation amount is not added, so that unnecessary approximation is avoided, burn-up calculation is performed directly according to the actual power level, and the confidence coefficient of the burn-up level is guaranteed.
Description
Technical Field
The invention relates to a burnup calculation device for burnable poison and novel fuel in a reactor, in particular to a method for calculating the burnup of non-fuel burnable poison in the reactor.
Background
The burn-up calculation based on the monte carlo method has two modes of normal power or normal flux, and the burn-up calculation is generally performed in a reactor according to input rated power. However, various burnable poisons may be employed in the core: the types can be divided into a dispersion type, a coating type and a separation type, wherein the latter two types do not contain fuel and thus can be called non-fuel burnable poison; there is little power in the burnup zone for non-fuel burnable poisons, so that such burnable poisons cannot be burnup in the normal power mode. In addition, certain fuel regions in the new core, such as thorium-based fuel for propagation, do not contain fissile nuclides at the beginning of life, have very low power at the beginning of life, and the ordinary power mode cannot be applied; while burnup calculations provide a constant flux burnup option, for fuel cells, constant flux calculations are prone to inaccuracies in power output.
At present, a fuel consumption calculation program based on a Monte Carlo method adopts a normal power mode or a normal flux mode to calculate fuel consumption, and the normal power mode is not suitable for fuel consumption calculation of ultra-low power regions such as non-fuel burnable poison, thorium base and the like; while the normally on mode may result in inaccuracies in the power output. Relevant research has been conducted abroad on the normal flux mode, and the corrected normal flux mode is adopted to ensure power output. It follows that the current treatment method is disadvantageous: the two calculation methods cannot be accurately and reasonably used, so that the respective defects cannot be avoided, the applicability is low, and the power statistics is not accurate; the normal flux mode of the correction approximation is adopted, and extra calculation amount is added.
Disclosure of Invention
The invention aims to provide a method for calculating the burnup of non-fuel burnable poison in a reactor, which solves the burnup problem of the current ultra-low power regions such as the non-fuel burnable poison, thorium base and the like under the condition of ensuring power output and achieves the aim of reasonably using two calculation methods.
The purpose of the invention is realized by the following technical scheme:
a method for calculating burnup of a non-fuel burnable poison in a reactor, comprising the steps of:
(a) calculating input total power by burnup in a reactor;
(b) distributing the power and flux of each burnup zone;
(c) and performing constant-power burnup calculation on the fuel area, and performing constant-flux burnup calculation on the non-fuel combustible toxic area.
According to the method, the burnup in the reactor is partitioned, and different burnup calculations are performed on each partition by determining the power and flux of the partition, so that each power consumption area adopts different burnup calculation modes, each power consumption area can realize a reasonable combustion mode, and different areas adopt reasonable burnup calculations to run more reasonably.
Said step (b) of distributing the power and flux of each burnup zone is performed according to the following steps:
(b1) the average fission energy per incident neutron produced in the i burnup zone is:
（1）
wherein E is the energy produced by the fission of each nuclide j, and the unit is megajoule/fission (MJ/fission), and the mole number of each nuclide of actinide in each region isWhere n is the nuclear density, V is the volume, NA is the Avogastron constant, fission cross sectionTarget, whereinIn cm 2;
(b2) flux normalized coefficient of：
Wherein,is the total power of the input; a is a constant，To average out the fission energy generated in the i burnup zone for each incident neutron,relative flux for zone i;
(b3) calculating relative flux of each burnup zone from Monte Carlo transportA is a constant，For the total power input, the flux for each zone, and the power for each zone, can be obtained:
wherein,is the absolute flux of the i-th zone,in order to normalize the coefficients for the flux,is the relative flux of the i-th zone,is the power of the i-th zone,a is a constant for averaging the fission energy generated in the burnup region by each incident neutron。
From (b 1) to (b 3), the absolute flux and power of each region are obtained from the species composition and the relative flux distribution of each region.
The step (c) adopts constant power burnup calculation for the fuel area, and the constant flux burnup calculation for the non-fuel combustible toxic area comprises the following steps:
(c1) setting a reference value;
(c2) comparing the ratio of power to flux with a reference value; if the ratio of the power to the flux is larger than the reference value, performing normal power burnup calculation; if the ratio of power to flux is less than the reference value, a constant flux burnup calculation is performed.
The invention adopts a mixed fuel consumption calculation mode based on a Monte Carlo method: for the fuel area, burning up in a normal power mode; aiming at ultra-low power regions such as non-fuel burnable poison, thorium base and the like, burning in a normal flux mode; the invention enlarges the application range of the burnup calculation based on the Monte Carlo method, and can process the burnup calculation of ultra-low power areas containing non-fuel burnable poison, thorium base and the like; the invention does not additionally increase the calculation amount, avoids unnecessary approximation, directly carries out the burnup calculation according to the actual power level and ensures the confidence coefficient of the burnup depth.
Compared with the prior art, the invention has the following advantages and beneficial effects:
the invention relates to a method for calculating the burnup of a non-fuel burnable poison in a reactor, which divides the burnup in the reactor, determines the power and flux of the division to calculate the different burnup for each division, realizes that each power consumption area adopts different burnup calculation modes, ensures that each power consumption area can realize a reasonable combustion mode, ensures that different areas adopt reasonable burnup calculation and run more reasonably;
the invention relates to a method for calculating the burnup of non-fuel burnable poison in a reactor, which adopts a mixed burnup calculation mode based on a Monte Carlo method: for the fuel area, burning up in a normal power mode; aiming at ultra-low power regions such as non-fuel burnable poison, thorium base and the like, burning in a normal flux mode; because the traditional normal power mode cannot accurately calculate the fuel consumption of a no-power or ultra-low-power area, and the normal flux mode can calculate the fuel consumption at any time, but the fuel consumption statistical deviation can be reduced by adding correction calculation, the method can process the fuel consumption calculation of the ultra-low-power areas containing non-fuel combustible poison, thorium base and the like, simultaneously does not additionally increase the calculated amount, avoids unnecessary approximation, directly performs the fuel consumption calculation according to the actual power level, and ensures the confidence coefficient of the fuel consumption depth.
Drawings
FIG. 1 is a schematic cross-sectional view of an IFBA cell in accordance with an embodiment of the present invention;
FIG. 2 is an IFBA cell10B species as a function of burnup.
Reference numbers and corresponding part names in the drawings:
1-air gap He, 2-ZrB2Film, 3-UO2And (3) a core block.
Detailed Description
The present invention will be described in further detail with reference to examples, but the embodiments of the present invention are not limited thereto.
Examples
As shown in fig. 1, for the burnup of a fuel zone and a non-fuel burnable zone in a reactor, in order to clearly show the implementation effect, the IFBA unit including only two burnup zones is used as an implementation object below, and a mixed burnup calculation mode is checked; IFBA is a burnable poison rod developed by West House company in pure UO2Coating ZrB on the outside of the fuel pellet 32Film 2, ZrB2The air gap He is on the outside of the membrane 2 and is calculated as follows:
(a) calculating input total power by burnup in a reactor;
(b1) the average fission energy per incident neutron produced in the i burnup zone is:
（1）
wherein E is the energy produced by the fission of each nuclide j, and the unit is megajoule/fission (MJ/fission), and the mole number of each nuclide of actinide in each region isWhere n is the nuclear density, V is the volume, NA is the Avogastron constant, fission cross sectionTarget, whereinIn cm 2;
(b2) flux normalized coefficient of：
Wherein,is the total power of the input; a is a constant，To average out the fission energy generated in the i burnup zone for each incident neutron,relative flux for zone i;
(b3) calculating relative flux of each burnup zone from Monte Carlo transportA is a constant，For the total power of the input, it is obtainedFlux per zone, and power per zone:
wherein,is the absolute flux of the i-th zone,in order to normalize the coefficients for the flux,is the relative flux of the i-th zone,is the power of the i-th zone,a is a constant for averaging the fission energy generated in the burnup region by each incident neutron. E.g., fuel zone flux 4.423659e at a burn-up step+14Power 7.493400e-02(ii) a Film zone flux 4.389200e of ZrB2+14Power 7.133032e-27；
(c1) Setting a reference value of 1.0E-20；
(c2) Comparing the ratio of power to flux with a reference value; if the ratio of the power to the flux is larger than the reference value, performing normal power burnup calculation; if the ratio of power to flux is less than the reference value, a constant flux burnup calculation is performed.
Since the data volume of the cross section, energy, etc. of each nuclear species is very large, only the values of the reference value, flux and power are given in the embodiment. FIG. 2 shows that the comparison between the calculated 10B mass change with the burnup and the commercial nuclear design software PARAGON and APOLLO2-F shows that the results are good, and the method has the function of the burnup calculation in the ultra-low power region such as non-fuel combustible poison without adding extra correction calculation amount and approximation.
The above description is only a preferred embodiment of the present invention, and is not intended to limit the present invention in any way, and all simple modifications and equivalent variations of the above embodiment according to the present invention are within the scope of the present invention.
Claims (3)
1. A method for calculating burnup of a non-fuel burnable poison in a reactor, comprising the steps of: (a) calculating input total power by burnup in a reactor;
(b) distributing the power and flux of each burnup zone;
(c) and performing constant-power burnup calculation on the fuel area, and performing constant-flux burnup calculation on the non-fuel combustible toxic area.
2. The method of claim 1, wherein said step (b) of allocating power and flux to each burnup zone is performed according to the steps of:
(b1) the average fission energy per incident neutron produced in the i burnup zone is:
（1）
wherein E is the energy produced by the fission of each nuclide j, and the unit is megajoule/fission (MJ/fission), and the mole number of each nuclide of actinide in each region isWhere n is the nuclear density, V is the volume, NA is the Avogastron constant, fission cross sectionTarget, whereinIn cm 2;
(b2) flux normalized coefficient of：
Wherein,is the total power of the input; a is a constant，To average out the fission energy generated in the i burnup zone for each incident neutron,is the relative flux of the i-th zone
(b3) Calculating relative flux of each burnup zone from Monte Carlo transportA is a constant，For the total power input, the flux for each zone, and the power for each zone, can be obtained:
wherein,is the absolute flux of the i-th zone,in order to normalize the coefficients for the flux,is the relative flux of the i-th zone,is the power of the i-th zone,a is a constant for averaging the fission energy generated in the burnup region by each incident neutron。
3. The method of claim 1 for calculating burnup of a non-fuel burnable poison in a reactor, wherein: the step (c) adopts constant power burnup calculation for the fuel area, and the constant flux burnup calculation for the non-fuel combustible toxic area comprises the following steps:
(c1) setting a reference value;
(c2) comparing the ratio of power to flux with a reference value; if the ratio of the power to the flux is larger than the reference value, performing normal power burnup calculation; if the ratio of power to flux is less than the reference value, a constant flux burnup calculation is performed.
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| CN106503446A (en) * | 2016-10-24 | 2017-03-15 | 中国原子能科学研究院 | A kind of computational methods of strong neutron field fission-product nucleus burnup |
| CN107273582A (en) * | 2017-05-23 | 2017-10-20 | 西安交通大学 | A kind of computational methods for fast neutron reactor neutron transport burnup coupling analysis |
| CN107766641A (en) * | 2017-10-16 | 2018-03-06 | 中国核动力研究设计院 | One kind calculates UO2The method of fuel fission gas rate of heat release |
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| JPH0640137B2 (en) * | 1986-08-01 | 1994-05-25 | 株式会社日立製作所 | Fuel assembly and boiling water reactor |
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| CN106282529A (en) * | 2015-05-29 | 2017-01-04 | 宝山钢铁股份有限公司 | A kind of hot-rolling heating furnace slab fuel consumption meter metering method |
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| CN106503446B (en) * | 2016-10-24 | 2019-03-12 | 中国原子能科学研究院 | A kind of calculation method of strong neutron field fission-product nucleus burnup |
| CN107273582A (en) * | 2017-05-23 | 2017-10-20 | 西安交通大学 | A kind of computational methods for fast neutron reactor neutron transport burnup coupling analysis |
| CN107273582B (en) * | 2017-05-23 | 2020-03-17 | 西安交通大学 | Calculation method for neutron transport burnup coupling analysis of fast neutron reactor |
| CN107766641B (en) * | 2017-10-16 | 2020-08-25 | 中国核动力研究设计院 | Calculate UO2Method for fuel fission gas heat release rate |
| CN107766641A (en) * | 2017-10-16 | 2018-03-06 | 中国核动力研究设计院 | One kind calculates UO2The method of fuel fission gas rate of heat release |
| CN110457802A (en) * | 2019-07-31 | 2019-11-15 | 上海交通大学 | The precision optimizing implementation method of simulation is checked for SFCOMPO burnup experiment benchmark problem |
| CN110457802B (en) * | 2019-07-31 | 2021-08-20 | 上海交通大学 | Precision optimization implementation method for SFCOMPO fuel consumption experiment benchmark question check simulation |
| CN112420223A (en) * | 2020-11-18 | 2021-02-26 | 中国核动力研究设计院 | Long-circulation refueling loading method for pressurized water reactor core based on gadolinium enrichment |
| CN113935567A (en) * | 2021-08-27 | 2022-01-14 | 中核龙原科技有限公司 | Quantitative assessment method for economic loss of nuclear power plant early shutdown refueling fuel |
| CN113935567B (en) * | 2021-08-27 | 2024-01-16 | 中核龙原科技有限公司 | Quantitative evaluation method for fuel economy loss of early shutdown refueling of nuclear power plant |
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