CN114003856A - Method for calculating environment radiation field in shutdown state of nuclear thermal propulsion reactor - Google Patents
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Abstract
A method for calculating an environment radiation field in a shutdown state of a nuclear thermal propulsion reactor comprises the following steps: 1. determining the geometric structure, the operation history, the fuel distribution, the shielding material and the structural parameters of the nuclear thermal propulsion reactor; 2. calculating the radioactive intensity and distribution of the nuclear thermal propulsion reactor operating products by using a TRITON control module of SCALE software; 3. calculating a neutron energy spectrum and a photon energy spectrum of the operation product by using an ORIGEN-S control module of SCALE software; 4. calculating the radiation of the environment outside the nuclear thermal propulsion reactor by using a multi-dimensional point nuclear analysis program QADS of SCALE software; 5. increasing the number of the calculation areas, jumping to the step 2 to perform new calculation, comparing the calculation results of the two times, and if the variation of the calculation results is not within the acceptable range, increasing the calculation areas to continue the calculation; and if the change of the calculation result is within the acceptable range, the number of calculation areas is not increased, and the calculation of the radiation field is further completed. The method of the invention can obtain accurate calculation results.
Description
Technical Field
The invention relates to the field of nuclear thermal propulsion reactors, in particular to a method for calculating an external environment radiation field in a shutdown state of a nuclear thermal propulsion reactor.
Background
The nuclear power propulsion has the great advantages of ultra-long endurance, strong maneuverability, high concealment and the like, and attracts the sight of the whole world. However, the nuclear thermal propulsion reactor can generate a large amount of radioactive substances during operation and after shutdown, and release a large amount of radiation, and meanwhile, due to economic considerations, the nuclear thermal propulsion reactor generally has no perfect radiation shielding device, so that a large amount of radiation pollution can be caused to the external environment, and the use and the storage of the nuclear thermal propulsion reactor are greatly influenced.
Disclosure of Invention
In order to overcome the above problems, an object of the present invention is to provide a method for calculating an external environment radiation field in a shutdown state of a nuclear thermal propulsion reactor, which considers the influence of uneven distribution of radioactive materials and performs calculation by gradually increasing the calculation area, so as to obtain the radiation field intensity distribution of the external environment in the shutdown state of the nuclear thermal propulsion reactor. The invention provides theoretical suggestion and guidance for the calculation of the environmental radiation in the shutdown state of the nuclear thermal propulsion reactor, and provides a method for designing the nuclear thermal propulsion reactor with high efficiency and safety.
In order to achieve the purpose, the invention adopts the following technical scheme:
a method for calculating an ambient radiation field in a shutdown state of a nuclear thermal propulsion reactor comprises the following steps:
step 1: determining the geometric structure, the operation history, the fuel distribution, the shielding material and the structural parameters of the nuclear thermal propulsion reactor;
step 2: TRITON is a multipurpose control module in SCALE software, couples a transport calculation program KENO and a burnup calculation program ORIGEN-S, and solves a neutron transport equation (1) and a burnup equation (2):
neutron transport equation:
the burnup equation:
in the formula
Omega-unit vector of direction of motion
Phi (r, omega, E) -neutron angular fluence rate/m at position r, with omega direction of motion and E energy-2·s-1
Phi (r, omega ', E') -neutron angular fluence rate/m with energy E 'at position r, motion direction omega', and energy E-2·s-1
r-spatial position/m
Σt-probability of neutron collision
ΣsNeutron moderation probability
Σf-probability of fission
E-energy/J
X (E) -neutron fission spectrum
V-neutron velocity/m.s-1
f (r, E '→ E, Ω' → Ω) — the energy changes from E 'to E, and the neutron whose direction of motion changes from Ω' to Ω accounts for the proportion of all other angles and colliding neutrons of energy
NiAtomic density/atom.cm of nuclide i-3
NjAtomic density/atom.cm of nuclide j-3
NkAtomic density of nuclide k/atom · cm-3
λiDecay constant of nuclide i
λjDecay constant of nuclide j
σiSpectral average neutron absorption cross section of nuclide i/b
σkSpectral average neutron absorption cross section/b of nuclide k
lij-branching ratio/% of radioactive decay of other nuclides
fik-branch ratio/% of the other nuclide k absorbing the neutron-producing nuclide i
Setting material parameters by using a multipurpose control module TRITON, establishing a geometric model of the nuclear thermal propulsion reactor, setting the running time and the running power, and calculating the radioactivity of fission products and actinide products after the nuclear thermal propulsion reactor is finished running and the radioactivity of each fuel region with different uranium concentrations; in the results output by the multipurpose control module TRITON, each fuel area with uranium concentration only outputs the radioactivity results of one fission product and one actinide product, the area which only outputs the radioactivity results of one fission product and one actinide product is regarded as a calculation area, and the radioactive substances and the fuel uranium concentration in the calculation area are regarded as uniform distribution; because each calculation region only outputs the radioactivity results of one fission product and actinide product when the multipurpose control module TRITON outputs the results, when a more detailed radioactive substance distribution result of a certain calculation region needs to be known, the region needs to be split into a plurality of calculation regions, the number of the calculation regions is increased, and the specific steps of splitting the calculation regions and increasing the number of the calculation regions are as follows:
1): when the multipurpose control module TRITON is used for setting material parameters, material numbers are added to materials in a calculation area needing to be split, namely a plurality of material numbers are created for one material at the same time;
2): when a multipurpose control module TRITON is used for establishing a geometric model of the nuclear thermal propulsion reactor, geometric modeling is carried out on a calculation region needing to be split again, the calculation region needing to be split is not regarded as a geometric body any more, but is split into a plurality of small geometric bodies for modeling; meanwhile, when setting material parameters, although the material of each small geometric body is the same, the material number of each small geometric body cannot be set to be the same and is sequentially set to be the material number created in 1);
3): adding the material number created in 1) into the material number setting set by the output result of the multipurpose control module TRITON;
4): after the steps are completed, when the multipurpose control module TRITON completes the calculation, calculation results of more calculation areas are obtained from the calculation results;
and step 3: inputting the calculation results of the radioactivity of the TRITON fission products and the actinide products of the multipurpose control module into an ignition energy consumption calculation program ORIGEN-S to calculate photon energy spectrums and neutron energy spectrums of the nuclear thermal propulsion reactor full stack and the operation products in each calculation region; the gamma ray source intensity and energy spectrum calculated by the ignition loss calculation program ORIGEN-S include X-rays, gamma rays, bremsstrahlung, spontaneous fission gamma rays and photons generated by gamma rays accompanying the (α, n) reaction, the nuclear data is stored in the binary format library of the ignition loss calculation program ORIGEN-S, and the photon energy spectrum of the user-directly specified energy group structure is calculated by the formula (3):
Ig＝Ia(Ea/Eg) (3)
in the formula
Ia-actual photon intensity/photons s in gamma library-1
Ea-actual photon energy/MeV
Eg-energy group mean energy/MeV
Ig-photon intensity/photons.s of energy group-1
The neutron source intensity and energy spectrum calculated by the ignition depletion calculation program ORIGEN-S includes spontaneous fission (α, n) reactions and (β) reactions, where (β) reactions are not important in typical spent fuels; the (α, n) reaction then calculates the effect of the surrounding medium by:
in the formula
S (E) -Total stopping force of Medium/b
σi(E) Of a nuclear species i: (α, n) reaction section/b
E-neutron energy/MeV
Yi,kThe energy emitted by the nuclide k is EαNeutron yield per neutrons s of alpha particles of (2)-1
N-Total atomic Density/atom. cm-3
Ni-atomic density/atom.cm of target nuclide-3
And 4, step 4: establishing a nuclear thermal propulsion reactor geometric model by using a multi-dimensional point nuclear analysis program QADS (quality and intensity), inputting the distribution and the neutron energy spectrum of each calculation area, setting a calculation reference point, and calculating the radiation dose of the reference point; aiming at a typical cylindrical reactor, by axially dividing the reactor into small sections of cylinders, creating a new input card for each section, and then adjusting the radial radioactive substance distribution in each input card through weight statements, the precise description of the radioactive substance distribution is realized; the QADS adopts a point kernel integration algorithm, and the equation is as follows:
in the formula
V-volume of source/m3
Mu-total attenuation coefficient at energy E
K-flux-dose conversion factor
B-dose cumulative factor
s-number of photons/photons s-1
E-photon energy/MeV
And 5: firstly, selecting some reference points, and only performing radiation dose calculation of the reference points before determining the number of calculation areas, wherein the selected reference points need to be uniformly distributed around a reactor and cannot be too far away from the reactor; after the first round of calculation is finished, increasing the number of calculation areas according to the method for dividing the calculation areas and increasing the number of calculation areas in the step 2, jumping to the step 2 to perform a new round of calculation, comparing the results of the previous and new rounds of calculation after the new round of calculation is finished, if the change of the calculation result is not within the acceptable range, continuing to increase the calculation areas, and recalculating until the change of the calculation result is within the acceptable range; if the change of the calculation result is within the acceptable range, the calculation region is selected sufficiently, the uneven distribution of the radioactive substance can be simulated, the calculation is carried out according to the calculation region setting of the new calculation, and the calculation of the whole radiation field is completed.
Compared with the prior art, the invention has the following outstanding characteristics:
(1) by increasing the number of calculation areas, a more accurate source item distribution result can be obtained, and the accurate calculation of the uneven distribution of the radioactive source can be realized; (2) the most economic and effective calculation region setting number can be searched, and the calculation efficiency and the calculation precision are improved; (3) the external environment radiation field caused by the operation products in the shutdown state of the nuclear thermal propulsion reactor can be accurately calculated.
Aiming at the existing problems, the invention provides a fine calculation method for the radiation of the external environment under the shutdown state of the nuclear thermal propulsion reactor, thereby providing a reference for the design and the safety of the nuclear thermal propulsion reactor.
Drawings
FIG. 1 is a flow chart of the method of the present invention.
Detailed Description
The invention is described in further detail below with reference to the following figures and detailed description:
the invention relates to a method for calculating an external environment radiation field in a shutdown state of a nuclear thermal propulsion reactor,
the nuclear thermal propulsion reactor has the characteristics of high energy density, small volume and light weight, and in order to realize miniaturization design and improve nuclear reactivity, the nuclear reactor necessarily adopts high-concentration uranium materials, and radioactive operation products are main radioactive source items during shutdown storage. The method comprises the steps of solving the radiation of the environment outside the reactor caused by radioactive operation products by using SCALE software, refining the calculated area by continuously increasing the number of the calculated areas in the reactor, obtaining the distribution condition of more refined operation products, and obtaining more accurate dose equivalent rate calculation results by inputting more accurate and detailed radiation sources when solving the dose equivalent rate; the method can calculate the external environment radiation caused by the operation products in the shutdown state of the nuclear thermal propulsion reactor, and can obtain an accurate dose equivalent rate calculation result in the calculation.
As shown in fig. 1, the method specifically includes the following steps:
step 1: determining the geometric structure, the operation history, the fuel distribution, the shielding material and the structural parameters of the nuclear thermal propulsion reactor;
step 2: TRITON is a multipurpose control module in SCALE software, couples a transport calculation program KENO and a burnup calculation program ORIGEN-S, and solves a neutron transport equation (1) and a burnup equation (2):
neutron transport equation:
the burnup equation:
in the formula
Omega-unit vector of direction of motion
Phi (r, omega, E) -neutron angular fluence rate/m at position r, with omega direction of motion and E energy-2·s-1
Phi (r, omega ', E') -neutron angular fluence rate/m with energy E 'at position r, motion direction omega', and energy E-2·s-1
r-spatial position/m
Σt-probability of neutron collision
ΣsNeutron moderation probability
Σf-probability of fission
E-energy/J
X (E) -neutron fission spectrum
V-neutron velocity/m.s-1
f (r, E '→ E, Ω' → Ω) — the energy changes from E 'to E, and the neutron whose direction of motion changes from Ω' to Ω accounts for the proportion of all other angles and colliding neutrons of energy
NiAtomic density/atom.cm of nuclide i-3
NjAtomic density/atom.cm of nuclide j-3
NkAtomic density of nuclide k/atom · cm-3
λiDecay constant of nuclide i
λjDecay constant of nuclide j
σiSpectral average neutron absorption cross section of nuclide i/b
σkSpectral average neutron absorption cross section/b of nuclide k
lij-branching ratio/% of radioactive decay of other nuclides
fikOther nuclide k-aspiratesBranch ratio/% of neutron-generating nuclide i
Setting material parameters by using a multipurpose control module TRITON, establishing a geometric model of the nuclear thermal propulsion reactor, setting the running time and the running power, and calculating the radioactivity of fission products and actinide products after the nuclear thermal propulsion reactor is finished running and the radioactivity of each fuel region with different uranium concentrations; in the results output by the multipurpose control module TRITON, each fuel area with uranium concentration only outputs the radioactivity results of one fission product and one actinide product, the area which only outputs the radioactivity results of one fission product and one actinide product is regarded as a calculation area, and the radioactive substances and the fuel uranium concentration in the calculation area are regarded as uniform distribution; because each calculation region only outputs the radioactivity results of one fission product and actinide product when the multipurpose control module TRITON outputs the results, when a more detailed radioactive substance distribution result of a certain calculation region needs to be known, the region needs to be split into a plurality of calculation regions, the number of the calculation regions is increased, and the specific steps of splitting the calculation regions and increasing the number of the calculation regions are as follows:
1): when the multipurpose control module TRITON is used for setting material parameters, material numbers are added to materials in a calculation area needing to be split, namely a plurality of material numbers are created for one material at the same time;
2): when a multipurpose control module TRITON is used for establishing a geometric model of the nuclear thermal propulsion reactor, geometric modeling is carried out on a calculation region needing to be split again, the calculation region needing to be split is not regarded as a geometric body any more, but is split into a plurality of small geometric bodies for modeling; meanwhile, when setting material parameters, although the material of each small geometric body is the same, the material number of each small geometric body cannot be set to be the same and is sequentially set to be the material number created in 1);
3): adding the material number created in 1) into the material number setting set by the output result of the multipurpose control module TRITON;
4): after the steps are completed, when the multipurpose control module TRITON completes the calculation, calculation results of more calculation areas are obtained from the calculation results;
and step 3: inputting the calculation results of the radioactivity of the TRITON fission products and the actinide products of the multipurpose control module into an ignition energy consumption calculation program ORIGEN-S to calculate photon energy spectrums and neutron energy spectrums of the nuclear thermal propulsion reactor full stack and the operation products in each calculation region; the gamma ray source intensity and energy spectrum calculated by the ignition loss calculation program ORIGEN-S include X-rays, gamma rays, bremsstrahlung, spontaneous fission gamma rays and photons generated by gamma rays accompanying the (α, n) reaction, the nuclear data is stored in the binary format library of the ignition loss calculation program ORIGEN-S, and the photon energy spectrum of the user-directly specified energy group structure is calculated by the formula (3):
Ig＝Ia(Ea/Eg) (3)
in the formula
Ia-actual photon intensity/photons s in gamma library-1
Ea-actual photon energy/MeV
Eg-energy group mean energy/MeV
Ig-photon intensity/photons.s of energy group-1
The neutron source intensity and energy spectrum calculated by the ignition depletion calculation program ORIGEN-S includes spontaneous fission (α, n) reactions and (β) reactions, where (β) reactions are not important in typical spent fuels; the (α, n) reaction then calculates the effect of the surrounding medium by:
in the formula
S (E) -Total stopping force of Medium/b
σi(E) -reaction section of (α, n) of nuclide i/b
E-neutron energy/MeV
Yi,kThe energy emitted by the nuclide k is EαNeutron yield per neutrons s of alpha particles of (2)-1
N-total atomsDensity/atom.cm-3
Ni-atomic density/atom.cm of target nuclide-3
And 4, step 4: establishing a nuclear thermal propulsion reactor geometric model by using a multi-dimensional point nuclear analysis program QADS (quality and intensity), inputting the distribution and the neutron energy spectrum of each calculation area, setting a calculation reference point, and calculating the radiation dose of the reference point; aiming at a typical cylindrical reactor, by axially dividing the reactor into small sections of cylinders, creating a new input card for each section, and then adjusting the radial radioactive substance distribution in each input card through weight statements, the precise description of the radioactive substance distribution is realized; the QADS adopts a point kernel integration algorithm, and the equation is as follows:
in the formula
V-volume of source/m3
Mu-total attenuation coefficient at energy E
K-flux-dose conversion factor
B-dose cumulative factor
s-number of photons/photons s-1
E-photon energy/MeV
And 5: firstly, selecting some reference points, and only performing radiation dose calculation of the reference points before determining the number of calculation areas, wherein the selected reference points need to be uniformly distributed around a reactor and cannot be too far away from the reactor; after the first round of calculation is finished, increasing the number of calculation areas according to the method for dividing the calculation areas and increasing the number of calculation areas in the step 2, jumping to the step 2 to perform a new round of calculation, comparing the results of the previous and new rounds of calculation after the new round of calculation is finished, if the change of the calculation result is not within the acceptable range, continuing to increase the calculation areas, and recalculating until the change of the calculation result is within the acceptable range; if the change of the calculation result is within the acceptable range, the calculation region is selected sufficiently, the uneven distribution of the radioactive substance can be simulated, the calculation is carried out according to the calculation region setting of the new calculation, and the calculation of the whole radiation field is completed. The invention recognizes that the acceptable range can be selected to be 1% and this value can be increased or decreased depending on the circumstances.
Claims (1)
1. A method for calculating an environmental radiation field in a shutdown state of a nuclear thermal propulsion reactor is characterized by comprising the following steps: the method comprises the following steps:
step 1: determining the geometric structure, the operation history, the fuel distribution, the shielding material and the structural parameters of the nuclear thermal propulsion reactor;
step 2: TRITON is a multipurpose control module in SCALE software, couples a transport calculation program KENO and a burnup calculation program ORIGEN-S, and solves a neutron transport equation (1) and a burnup equation (2):
neutron transport equation:
the burnup equation:
in the formula
Omega-unit vector of direction of motion
Phi (r, omega, E) -neutron angular fluence rate/m at position r, with omega direction of motion and E energy-2·s-1
Phi (r, omega ', E') -neutron angular fluence rate/m with energy E 'at position r, motion direction omega', and energy E-2·s-1
r-spatial position/m
Σt-probability of neutron collision
ΣsNeutron moderation probability
Σf-probability of fission
E-energy/J
X (E) -neutron fission spectrum
V-neutron velocity/m.s-1
f (r, E '→ E, Ω' → Ω) — the energy changes from E 'to E, and the neutron whose direction of motion changes from Ω' to Ω accounts for the proportion of all other angles and colliding neutrons of energy
NiAtomic density/atom.cm of nuclide i-3
NjAtomic density/atom.cm of nuclide j-3
NkAtomic density of nuclide k/atom · cm-3
λiDecay constant of nuclide i
λjDecay constant of nuclide j
σiSpectral average neutron absorption cross section of nuclide i/b
σkSpectral average neutron absorption cross section/b of nuclide k
lij-branching ratio/% of radioactive decay of other nuclides
fik-branch ratio/% of the other nuclide k absorbing the neutron-producing nuclide i
Setting material parameters by using a multipurpose control module TRITON, establishing a geometric model of the nuclear thermal propulsion reactor, setting the running time and the running power, and calculating the radioactivity of fission products and actinide products after the nuclear thermal propulsion reactor is finished running and the radioactivity of each fuel region with different uranium concentrations; in the results output by the multipurpose control module TRITON, each fuel area with uranium concentration only outputs the radioactivity results of one fission product and one actinide product, the area which only outputs the radioactivity results of one fission product and one actinide product is regarded as a calculation area, and the radioactive substances and the fuel uranium concentration in the calculation area are regarded as uniform distribution; because each calculation region only outputs the radioactivity results of one fission product and actinide product when the multipurpose control module TRITON outputs the results, when a more detailed radioactive substance distribution result of a certain calculation region needs to be known, the region needs to be split into a plurality of calculation regions, the number of the calculation regions is increased, and the specific steps of splitting the calculation regions and increasing the number of the calculation regions are as follows:
1): when the multipurpose control module TRITON is used for setting material parameters, material numbers are added to materials in a calculation area needing to be split, namely a plurality of material numbers are created for one material at the same time;
2): when a multipurpose control module TRITON is used for establishing a geometric model of the nuclear thermal propulsion reactor, geometric modeling is carried out on a calculation region needing to be split again, the calculation region needing to be split is not regarded as a geometric body any more, but is split into a plurality of small geometric bodies for modeling; meanwhile, when setting material parameters, although the material of each small geometric body is the same, the material number of each small geometric body cannot be set to be the same and is sequentially set to be the material number created in 1);
3): adding the material number created in 1) into the material number setting set by the output result of the multipurpose control module TRITON;
4): after the steps are completed, when the multipurpose control module TRITON completes the calculation, calculation results of more calculation areas are obtained from the calculation results;
and step 3: inputting the calculation results of the radioactivity of the TRITON fission products and the actinide products of the multipurpose control module into an ignition energy consumption calculation program ORIGEN-S to calculate photon energy spectrums and neutron energy spectrums of the nuclear thermal propulsion reactor full stack and the operation products in each calculation region; the gamma ray source intensity and energy spectrum calculated by the ignition loss calculation program ORIGEN-S include X-rays, gamma rays, bremsstrahlung, spontaneous fission gamma rays and photons generated by gamma rays accompanying the (α, n) reaction, the nuclear data is stored in the binary format library of the ignition loss calculation program ORIGEN-S, and the photon energy spectrum of the user-directly specified energy group structure is calculated by the formula (3):
Ig＝Ia(Ea/Eg) (3)
in the formula
Ia-actual photon intensity/photons s in gamma library-1
Ea-actual photon energy/MeV
Eg-energy group mean energy/MeV
Ig-photon intensity/photons.s of energy group-1
The neutron source intensity and energy spectrum calculated by the ignition depletion calculation program ORIGEN-S includes spontaneous fission (α, n) reactions and (β) reactions, where (β) reactions are not important in typical spent fuels; the (α, n) reaction then calculates the effect of the surrounding medium by:
in the formula
S (E) -Total stopping force of Medium/b
σi(E) -reaction section of (α, n) of nuclide i/b
E-neutron energy/MeV
Yi,kNuclear k nuclearThe energy of the radiation is EαNeutron yield per neutrons s of alpha particles of (2)-1
N-Total atomic Density/atom. cm-3
Ni-atomic density/atom.cm of target nuclide-3
And 4, step 4: establishing a nuclear thermal propulsion reactor geometric model by using a multi-dimensional point nuclear analysis program QADS (quality and intensity), inputting the distribution and the neutron energy spectrum of each calculation area, setting a calculation reference point, and calculating the radiation dose of the reference point; aiming at a typical cylindrical reactor, by axially dividing the reactor into small sections of cylinders, creating a new input card for each section, and then adjusting the radial radioactive substance distribution in each input card through weight statements, the precise description of the radioactive substance distribution is realized; the QADS adopts a point kernel integration algorithm, and the equation is as follows:
in the formula
V-volume of source/m3
Mu-total attenuation coefficient at energy E
K-flux-dose conversion factor
B-dose cumulative factor
s-number of photons/photons s-1
E-photon energy/MeV
And 5: firstly, selecting some reference points, and only performing radiation dose calculation of the reference points before determining the number of calculation areas, wherein the selected reference points need to be uniformly distributed around a reactor and cannot be too far away from the reactor; after the first round of calculation is finished, increasing the number of calculation areas according to the method for dividing the calculation areas and increasing the number of calculation areas in the step 2, jumping to the step 2 to perform a new round of calculation, comparing the results of the previous and new rounds of calculation after the new round of calculation is finished, if the change of the calculation result is not within the acceptable range, continuing to increase the calculation areas, and recalculating until the change of the calculation result is within the acceptable range; if the change of the calculation result is within the acceptable range, the calculation region is selected sufficiently, the uneven distribution of the radioactive substance can be simulated, the calculation is carried out according to the calculation region setting of the new calculation, and the calculation of the whole radiation field is completed.
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