CN106815391A - A kind of bentonite Radionuclide Migration appraisal procedure for being based on two Scale Models - Google Patents
A kind of bentonite Radionuclide Migration appraisal procedure for being based on two Scale Models Download PDFInfo
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Abstract
The present invention relates to a kind of bentonite Radionuclide Migration appraisal procedure for being based on two Scale Models.Be considered as bentonite research object by cluster micro-scale and consider that the macro-scale of characteristic length is constituted by the present invention, basic model framework is still continued to use in bentonite macro-scale, specific absorption is considered in cluster micro-scale, the mechanism processes such as reaction, the data such as the chemical composition wanted needed for cluster dimension calculation are calculated by macro-scale and provided, cluster dimension calculation result returns to macro-scale model in the form of apparent partition coefficient, nuclein migration result is calculated in macro-scale model, so as to set up the two yardstick Mathematical Modelings of association bentonite both macro and micro two characteristic dimensions of cluster.The model by obtaining data and model being calculated, and with contrasted using model at present, further rationalize model.
Description
Technical field
The invention belongs to radioactive-waste disposal technical field, and in particular to a kind of to be based in the bentonite of two Scale Models
Nuclein migration appraisal procedure.
Background technology
High-level radwaste (High Level Radioactive Waste, abbreviation high-level waste, HLW) is mainly come
From the high-level radioactive liquid waste (abbreviation high activity liquid waste) in nuclear fuel reprocessing plant, and directly work as the weary of Waste disposal on a small quantity
Fuel element.High activity liquid waste includes the raffinate of uranium plutonium co-decotamination cycle generation in spent fuel reprocessing process, and uranium passivation
The part that the subsequent handlings such as circulation, plutonium passivation cycle are produced disposes waste liquid.In last handling process, what is contained in spentnuclear fuel is non-volatile
Property fission product is substantially all and enters into high activity liquid waste, that is, high activity liquid waste is contained more than 99% in nuclear fuel reprocessing process
Radionuclide, constitute the main body of high-level waste.
High-level waste has that radioactive activity high, nucleic long half time, toxicity are big, heat generation rate is high, chronic exposure harm is tight
The features such as weight, the mankind and its natural environment depended on for existence are existed with greatly long-term potential hazard；According to China 2005
The nuclear power developing planning of formulation, the year two thousand twenty nuclear power installed capacity is up to 4 × 107kW, building 1.8 × 107kW of installed capacity, I
Large-scale nuclear fuel reprocessing plant of state plans in being run after 2025, will produce hundreds of cubic metres of high activity liquid waste every year when the time comes, with
The further expansion of nuclear power scale, more high activity liquid wastes can be also produced.Therefore its safe disposal is the utilization of relation nuclear technology, core
Can sustainable development significant problem, the core concept of disposal be how high-level waste and environment for human survival security isolation,
To ensure the safety of the mankind and its environment.
High-level waste geology treatment system is by high-level waste firming body, waste canister and its external packing, buffering/backfill material
Material, disposal storehouse country rock composition, former three constitute artificial barrier, and country rock is the natural cover for defense.Buffering/backfilling material is last one
Artificial barrier, the selection of its material and engineering characteristic have significant impact, buffering/return to the safety of high-level waste geology treatment system
Filling chock material as the engineering barrier layer portions in Nuclear waste disposal system, be filled in waste canister and its external packing and country rock it
Between, it should play a part of to include：(1) engineering barrier effect, safeguards the stability of disposal library structure, buffers pressure from surrounding rock pair
The influence of dedicated waste tanks；(2) hydraulics barrier action, is filled in around waste canister and blocks crack, hole on country rock surface,
Prevent or delay underground water (solution) from reaching waste canister surface；(3) chemical barrier effect, limitation oxidant reaches waste canister
Surface, delays container to protection period of high-level waste；And when waste canister is worn by erosion, high-level waste firming body receives underground water etch
When disengaging nucleic, block migration of the nucleic to country rock.(4) conductive force, conduction high-level waste Radionuclide that should be able to be faster declines
Become the heat for producing, it is to avoid the accumulation of heat.Considered based on more than, bentonite clay material is with its extremely low permeability and excellent suction
Attached performance turns into the first-selection of high-level waste geology treatment system buffer material.
From the point of view of geological disposal safety evaluation angle, an extremely crucial problem is, thousand, Wan Nianhou, work as waste packaging
Container is worn by erosion, when radionuclide is leached and turns into inevitable in high-level waste firming body under groundwater erosion, bentonite buffering
Material can want to obtain quantifying of being migrated in bentonite padded coaming of Trace elements to block the migration of nucleic in much degree
Changing Pattern of the nuclein migration in extraneous physics, electrochemical conditions change, only relies on laboratory in information, and long time scale
Experiment is inadequate, it is necessary on the basis of experimental study, the transition process mechanism based on nucleic in bentonite, and foundation can
The pure mathematics model of the process is described, and using the model to Hlw Geological Repository bentonite padded coaming Radionuclide
Transition process does quantitative analysis and prediction.
Migration of the nucleic in bentonite will be influenceed by many physics, chemical factor, wherein the most key is several
Factor includes：The reaction and absorption and bentonite of seepage flow, nucleic containing radionuclide solution in bentonite in swelling soil pores
The diffusion of Radionuclide.
The adjoint Reaction Mechanisms too complex during backfilling material actual migration is buffered of nucleic, is related to difference
Electrochemical conditions under the geochemical reaction such as absorption, ion exchange, complexing, these complex reactions have impact on nucleic in bentonite
The distribution condition be detained, migrate, decides and finally migrate off bentonitic Nuclear analysis.Basic model is to this complex process
Simplification is done, bentonite Radionuclide has been described using isothermal linearity Adsorption Model and is detained, is migrated distribution condition, obtained by testing
Take related distribution coefficient.The advantage of so processing mode is easy for model and calculates and solve, and parameter is easy to by testing acquisition, but
This simple method of salary distribution also necessarily masks many details during actual migration simultaneously, brings certain error,
It is therefore desirable to set up more rational bentonite Radionuclide Migration model.
The content of the invention
Technology provided by the present invention, the purpose is to instruct high-level waste geology treatment safety evaluation to buffer backfill in working
Material Radionuclide Migration is calculated.
Absorption and nucleic diffusion of the present invention first to bentonitic physics, chemical property, seepage flow, nucleic in bentonite
Etc. the experimental studies results of aspect do combing analysis, and the induction and conclusion scale-model investigation present situation of bentonite Radionuclide Migration,
The theoretical digital-to-analogue that description nucleic is migrated in bentonite is set up on the basis of this, nucleic is in bentonite in solution analysis long time scale
In distribution and nuclein migration flux, and investigate the influence of different physics, chemical factor to nuclein migration, and set up two yardsticks
Model.
Be considered as bentonite research object by cluster micro-scale and consider that the macro-scale of characteristic length is constituted by the present invention,
Basic model framework is still continued to use in bentonite macro-scale, specific absorption, reaction etc. are considered in cluster micro-scale
The data such as mechanism process, the chemical composition wanted needed for cluster dimension calculation are calculated by macro-scale and provided, cluster dimension calculation
Result returns to macro-scale model in the form of apparent partition coefficient, and nuclein migration knot is calculated in macro-scale model
Really, so as to set up the two yardstick Mathematical Modelings of association bentonite both macro and micro two characteristic dimensions of cluster.
Model of the invention by obtaining data and model being calculated, and with contrasted using model at present, enter
One step rationalizes model.
Brief description of the drawings
Fig. 1 is the concepts of scale model schematic of bentonite of the present invention two.
Specific embodiment
The present invention is described in detail with reference to the accompanying drawings and examples.
The core of bentonite nuclein migration process model amendment is how more rational description nucleic is in bentonite hole
Distribution in gap underground water and bentonite solid phase, transition process model realization this purpose by setting up two yardsticks of the invention.
Be considered as bentonite research object by cluster micro-scale and consider that the macro-scale of characteristic length is constituted by the present invention
（As shown in Figure 1）, basic model framework is still continued to use in bentonite macro-scale, consider specific in cluster micro-scale
The data such as the mechanism processes such as absorption, reaction, the chemical composition wanted needed for cluster dimension calculation are calculated by macro-scale and provided, group
Cluster dimension calculation result returns to macro-scale model in the form of apparent partition coefficient, and core is calculated in macro-scale model
Plain migration results, so as to set up the two yardstick Mathematical Modelings of association bentonite both macro and micro two characteristic dimensions of cluster.
Cluster Scale Model is set up below, the concept based on average magnitude regards homogeneous to intend in the microcosmic cluster of bentonite, group
Chemical constituent distribution, pressure etc. are all uniform in cluster, do not exist quality, barometric gradient in cluster, only consider chemistry in cluster
Chemical reaction equilibrium between species.
In general, cause the reaction that nucleic exchanges between liquid phase and solid phase mainly include ion-exchange reactions,
Surface complex reaction and precipitation/dissolving reaction, in addition complex reaction in the liquid phase can form colloid, most colloid meetings
Stopped by hole and be detained, thus it is contemplated.For different nucleic, its key reaction is selected, analysis is balanced, with ion
As a example by exchange interaction：
Wherein n is the chemical valence of ion 1, and m is the chemical valence of ion 2, C1It is the concentration of the solution of ion component 1,Be from
1 solid concentration of subgroup point,It is the solid concentration of ion component 2, C2It is the solution phase concentration of ion component 2.It is fixed according to mass action
Rule, the thermodynamic equilibrium constant of the ion-exchange reactions can be expressed as：
Items are the thermodynamics concentration or activity of corresponding generation ion-exchange reactions species in formula bracket.Obviously, it is right
Certain nuclide concentration in bentonite Interstitial Water and in bentonite solid phase, when equilibrium is reached, can be represented with above formula.
If the initial concentration of solution and solid phase Radionuclide is A1And A2, the corresponding initial concentration for exchanging species is B1And B2, that
When obviously reaching balance, if exchange capacity of the nucleic between solid liquid phase is x, then the exchange capacity for exchanging species is
Corresponding expression formula is when then reaching thermodynamical equilibrium：
So in the case of the known reaction equilibrium constant, exchange capacity can be obtained, it is possible to calculate corresponding absorption
Distribution coefficient is:
So when the reaction being related to no longer is one, but when n reaction, then for liquid phase Radionuclide
To general coefficient of distribution be：
To the distribution coefficient of each single reaction, then for：
And xiValue may be for just, it is also possible to be negative, reacting balance expression by each is been described by, such as the
For n reaction：
Obviously reacted for n, can set up n nonlinear equation, simultaneous solution this by n equation constitute it is non-linear
Equation group, obtains the solid-liquid exchange capacity reacted for each, then substitutes into formula (5), and formula (6) can be obtained by the cluster
The distribution coefficient of total adsorption isothermequation and single reaction.
In realistic model calculating, the initial concentration A of cluster liquid phase Radionuclide1, then need by the type meter of macro-scale mould 5
Calculate,
The gross balance equation that description nucleic is migrated in bentonite：
According to linear adsorption equilibrium relation
K in formuladIt is the adsorption isothermequation of nucleic.
Further merging is done to formula (10) using formula (9), and the decay coefficient for thinking dissolving mutually and in absorption phase is identical
, can obtain：
R is delay factor in formula, and its expression formula is：
Formula also relates to percolation flow velocity q in (11), and its calculating formula is：
Wherein h is the head along bentonite radial direction, can be obtained by solving the saturation subsurface flow differential equation：
S in formulawIt is the unit coefficient of storage of pore media, each parameter interpretation is shown in basic model (i.e. formula 9 to 14), while
The initial concentration that it is also required to provide solid phase Radionuclide is A2：
For n reaction, n equation solution can be set up.Corresponding initial concentration for exchanging species is B1And B2, can be same
Reason sets up the corresponding differential equation.
Two Scale Model need to use Numerical Methods Solve, in actual solution procedure, macro-scale model is solved first,
Walked with time difference, often solve a step, it is right that the concentration information of the nucleic for obtaining and each species is substituted into microcosmic cluster models solution
The distribution coefficient answered, then carries out next step calculating, and so on, directly distribution coefficient return macro-scale model is calculated
All calculated to completion.
Obviously, those skilled in the art can carry out various changes and modification without deviating from essence of the invention to the present invention
God and scope.So, if these modifications of the invention and modification are belonged to the model of the claims in the present invention and its equivalent technology
Within enclosing, then the present invention is also intended to comprising these changes and modification.
Claims (5)
1. a kind of bentonite Radionuclide Migration appraisal procedure for being based on two Scale Models, it is characterised in that methods described includes as follows
Step：
(1) bentonite is divided into by cluster micro-scale model and considers that the macro-scale model of characteristic length is constituted；
(2) basic model framework is used in the macro-scale model；
(3) consider specific mechanism process in the cluster micro-scale model, cluster micro-scale model calculate needed for will
Data calculated by macro-scale model and provide, cluster micro-scale the model calculation returns in the form of apparent partition coefficient
Macro-scale model；
(4) nuclein migration result is calculated in macro-scale model, so as to set up association bentonite both macro and micro cluster
Two two Scale Models of characteristic dimension；
(5) according to the situation of above-mentioned nuclein migration outcome evaluation bentonite Radionuclide Migration.
2. the bentonite Radionuclide Migration appraisal procedure of two Scale Models is based on as claimed in claim 1, it is characterised in that：
The basic model framework is described bentonite Radionuclide using isothermal linearity Adsorption Model and is detained, migrates distribution condition,
Related distribution coefficient is obtained by testing.
3. the bentonite Radionuclide Migration appraisal procedure of two Scale Models is based on as claimed in claim 1, it is characterised in that：
The mechanism process includes absorption and/or reacts.
4. the bentonite Radionuclide Migration appraisal procedure of two Scale Models is based on as claimed in claim 3, it is characterised in that：
The reaction includes ion-exchange reactions, surface complex reaction and precipitation/dissolving reaction.
5. the bentonite Radionuclide Migration appraisal procedure of two Scale Models is based on as claimed in claim 1, it is characterised in that：
Data in the step (3) are nucleic and the concentration information of each species.
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114386227A (en) * | 2021-11-30 | 2022-04-22 | 中国辐射防护研究院 | Upscaling method for radionuclide migration parameters |
| CN115310026A (en) * | 2022-10-12 | 2022-11-08 | 海南浙江大学研究院 | Bentonite expansive force prediction method and system considering ionic hydration energy |
| CN117807681A (en) * | 2024-01-02 | 2024-04-02 | 中国恩菲工程技术有限公司 | Digital twin mine modeling methods and devices, media, and equipment |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114386227A (en) * | 2021-11-30 | 2022-04-22 | 中国辐射防护研究院 | Upscaling method for radionuclide migration parameters |
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| CN115310026A (en) * | 2022-10-12 | 2022-11-08 | 海南浙江大学研究院 | Bentonite expansive force prediction method and system considering ionic hydration energy |
| CN117807681A (en) * | 2024-01-02 | 2024-04-02 | 中国恩菲工程技术有限公司 | Digital twin mine modeling methods and devices, media, and equipment |
| CN117807681B (en) * | 2024-01-02 | 2024-05-17 | 中国恩菲工程技术有限公司 | Digital twin mine modeling method and device, medium and equipment |
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