CN106815390A - The construction method of high-level waste glass solidified body nuclein migration hydrolysis kinetic model - Google Patents
The construction method of high-level waste glass solidified body nuclein migration hydrolysis kinetic model Download PDFInfo
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Abstract
The present invention relates to a kind of construction method of high-level waste glass solidified body nuclein migration hydrolysis kinetic model, the glass established in view of the composition of glass, the pH value of solution and temperature hydrolyzes reaction kinetics equation, and consider that all release and part discharge two kinds of situations to nucleic, glass solidified body Radionuclide Migration model is established, so that Sources term analysis and nuclein migration evaluation work in effectively instructing high-level waste geology treatment safety evaluation to work.
Description
Technical field
The present invention relates to the research of Nuclear waste disposal technology, and in particular to a kind of high-level waste glass solidified body nucleic is moved
Move the construction method of hydrolysis kinetic model.
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, is building installed capacity 1.8 × 107KW, 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.
Glass solidification treatment is that the currently the only high activity liquid waste for obtaining commercial Application reorganizes and outfit method, high activity liquid waste through glass
The height obtained after curing process is put glass solidified body and is placed in packaging container of metal, then it is that current people can to carry out deep geological disposal
The safest, reasonable the Engineering Approach for receiving.
Because radionuclide is inclusive in glass solidified body, all possible radioactivity is derived from glass solidification
Body, therefore glass solidified body is the source item of radionuclide release and transport；And geological stratification is moved through qualitative change for a long time, underground aqueous corrosion
Etc. reason, after engineering barrier failure, glass solidified body is the primary control device for hindering radionuclide release.Based on the two
Reason must be analysed in depth to glass solidified body, understand its physics, the chemical change mechanism under varying environment situation, and
Its evolution on thousand, ten thousand years even more long time scale and during radionuclide release and transport situation.
In deep geological stratification, the evolution of glass solidified body will be subject to heat, stress, radiation, microorganism, underground water and chemistry anti-
The combined influence of factors should be waited, but the coupling influence of underground water and chemical reaction is to cause glass solidified body to degrade
The main cause of (alteration, dissolving, leaching, nuclein migration).
Be understand groundwater environment in glass solidified body alteration, dissolving, leaching process mechanism, from the seventies in last century with
Come, substantial amounts of laboratory experiment, subterranean laboratory checking test and natural kind have done in domestic and international relevant research laboratory
Than research.Because change behavior of the glass solidified body in true geologic medium is very complicated, although to glass in groundwater environment
Firming body behavioral mechanism obtains some basis common recognitions, but still has many queries, dispute to its detailed mechanism, so far without complete
Reach an agreement.On the other hand, because the time of laboratory test is only in a shorter time scale, typically only several years,
The glass solidified body dissolution experiment time is most long also only 26 years in being currently known document, due to glass solidified body own physical, changes
Learn the complexity that property and residing groundwater environment composition change on a larger time scale, it is clear that being impossible be by laboratory
Under the conditions of short-term glass solidified body situation of change, data directly speculate its Long-term evolution regularity；And in Natural analogy research
Class glass solidified body is with glass solidified body and similar in the absence of complete physics phase Sihe chemistry, and the data obtained is also only as benefit
Fill and prove.Therefore, in order to predict the high evolution for putting glass solidified body in long time scale and during radionuclide release
Put migration situation, it is necessary on the basis of the behavior mechanism of action of the glass solidified body in complicated groundwater environment is understood, based on
Some experimental facts, analysis glass solidified body and environmental groundwter interact, and set up and consider that glass solidified body and underground water are made
With mechanism, the theoretical model of glass solidified body physics, chemical change and radionuclide release and transport process can be described.
The content of the invention
It is an object of the invention to provide a kind of high-level waste glass solidified body nuclein migration hydrolysis kinetic model
Construction method, so as to instruct Sources term analysis during high-level waste geology treatment safety evaluation works to be calculated with nuclein migration.
Technical scheme is as follows：A kind of high-level waste glass solidified body nuclein migration hydrolysis kinetic model
Construction method, set up following hydrolysis kinetic equation：
In formula,
rateG：The dissolution rate of glass, g/ (m2·d)；
Effective speed constant, is only dependent upon glass composition, and unit is quality/(the area time)；
η：On H+ reactions to series, dimensionless；
Ea：The activation energy of ratedeterming step, kJ/mol；
R:Gas constant, 8.314J/ (molK)；
T:Temperature, K；
Q:Silicic acid concentration in solution, mass/volume；
K：The apparent silicic acid saturated concentration of glass, mass/volume；
klong：Long-term dissolution rate, quality/(area time)；
The dissolution rate of the glass obtained according to above hydrolysis kinetic equation, calculates radioactivity under two kinds of extreme cases
The rate of release of nucleic：
(1) whole release conditions, when glass solidified body dissolves, it is molten that the radionuclide for being contained all is discharged into main body
In liquid, this is the maximum of radionuclide rate of release in glass solidified body；
(2) part release conditions, when glass solidified body dissolves, the colloid for being set with same quality enters bulk solution
In, but nucleic is still inclusive in colloid, and only the nucleic in colloid pore water is discharged into bulk solution, and this is glass solidified body
The minimum of middle radionuclide rate of release.
Further, the structure side of high-level waste glass solidified body nuclein migration hydrolysis kinetic model as described above
Method, wherein, also including being reduced to the hydrolysis kinetic equation set up：
Wherein, kEValue need to consider glass composition influence, including waste content inhomogeneities, the shadow of solution composition
Ring, and solution acid-base property, carry out different values；η and EaAcid-base property according to solution carries out value：
For acid solution：
kE_acidicMaximum be 1.15 × 107g/(m2D),
kE_acidicMinimum value or most probable value be 8.41 × 103g/(m2D),
η=- 0.49,
Ea=31kJ/mol；
For alkaline solution：
kE_alkalineMaximum be 3.47 × 104g/(m2D),
kE_alkalineMinimum value or most probable value be 28.2g/ (m2D),
η=0.49,
Ea=69kJ/mol.
Further, the structure side of high-level waste glass solidified body nuclein migration hydrolysis kinetic model as described above
Method, wherein, when all being discharged for radionuclide, radionuclide rate of release is：
RRN=rateG×S×IRN
In formula,
RRN：The rate of release of radionuclide, g/day；
rateG：The dissolution rate of glass, g/ (m2·d)；
S:The glass surface area contacted with water, m2；
IRN：Radionuclide RN total amounts in glass, g (RN)/g (glass) (radiation included in i.e. every gram vitreum
The quality of property nucleic)；
Wherein, the surface area S that glass is initially contacted with water0Calculating use following formula：
S0=fexposure×(2πr0 2+2πr0×L0)
In formula,
S0：Glass includes the initial exposed surface area in crack, m2；
r0：The initial radium of glass, m；
L0：The initial length of glass, m；
fexposureIt is the exposure factor, value is 4-17；
Residual surface S (glass surface area for being contacted with water) in glass degradation process is：
S=fexposure×SSP×(M0-∑M)
In formula,
SSP：Glass geometry specific surface area, object geometrical surface/mass of object；
M0:Glass solidified body initial mass；
∑M:Glass solidified body has dissolved quality；
At current time step end, the quality of glass degraded is calculated by following formula：
M (t)=rateG×t×S
In formula,
M(t)：In the quality of current time step end glass degraded；
S：In the glass residual surface of current time step；
t：With the duration of the time step of speed identical time quantum；
In the remaining glass quality Σ M in current time step endtCalculated by following formula：
ΣMt=Σ Mt-1-M(t)
In formula,
ΣMt-1：Remaining glass quality before current time step.
Further, the structure side of high-level waste glass solidified body nuclein migration hydrolysis kinetic model as described above
Method, wherein, when being discharged for radionuclide part, radionuclide rate of release is：
R'RN=VW×SORN
In formula,
R'RN：The minimum release rate of radionuclide, mol/day；
VW：Corrode the volume of layer pore water, m3；
SORN：Radionuclide solubility, mol/L；
Corrode the volume V of layer pore waterWObtained by following formula：
VW=VR×φ
In formula,
VR：Corrode the volume of layer；
φ：The porosity of alterated layer.
Further, the porosity φ of described alterated layer is：
φ=XW×ρR/ρW
In formula,
φ：Corrode the porosity of layer；
XW：Corrode the mass fraction of layer reclaimed water；
ρR：Corrode the density of layer；
ρW：The density of hole reclaimed water；
Corrode the density p of layerRThe density p that can be crystallized according to clayC, the density p of pore waterW, and hole accounts for by water completely
According to when porosityBe given：
Further, the structure side of high-level waste glass solidified body nuclein migration hydrolysis kinetic model as described above
Method, wherein, it is also contemplated that the decay of nucleic, decay rate equation is as follows：
Mi(t)=Mi(0)e-λt
In formula,
Mi(t)：Nucleic i is in time t quality, g；
Mi(0)：The initial mass of nucleic i, g；
λ：Decay coefficient；
t：Decay time, s；
e：Natural logrithm.
Beneficial effects of the present invention are as follows：Present invention firstly provides the hydrolysis kinetic mould of glass solidified body dissolving
Type, and the method that specific nuclein migration is calculated is developed, constructed model can effectively instruct the source item of safety evaluation
The development of evaluation work.
Specific embodiment
With reference to specific embodiment, the present invention will be described in detail.
The construction method of high-level waste glass solidified body nuclein migration hydrolysis kinetic model provided by the present invention,
The hydrolysis kinetic equation of the composition, the pH value of solution and temperature that consider glass is established, equation can be expressed as：
In formula,
Effective speed constant, is only dependent upon glass composition, and unit is quality/(the area time)；
η：On H+ reactions to series, dimensionless；
Ea：The activation energy of ratedeterming step, kJ/mol；
R:Gas constant, 8.314J/ (molK)；
T:Temperature, K；
Q:Silicic acid concentration in solution, mass/volume；
K：The apparent silicic acid saturated concentration of glass, mass/volume；
klong：It is long-term dissolution rate, quality/(area time).
Because under the conditions of storehouse is disposed, dissolution rate will not become zero, and for the ease of performing, klongWith affinity
Change can be combined into effective speed constant.Effective speed constant can express the change of the different glass composition in storehouse is disposed.
Therefore, the formula (1) of model can be reduced to：
The glass degradation model is it needs to be determined that three parameter values：kE, η and Ea, and two variables：T and pH.kEValue need to be examined
Consider the influence of glass composition, including waste content inhomogeneities, and solution composition influence, different situations need to take not
With value, for acid solution and aqueous slkali, these parameters have different values.
For η and Ea, all glass compositions use identical value, but are used respectively in acid and alkaline solution independent
Parameter value.Constant value η=- 0.49 and Ea=31kJ/mol is used for acid solution, constant value η=0.49 and Ea=69kJ/mol is used
In alkaline solution.Substitution formula (2) can obtain down two formulas：
K in formulaE_acidicAnd kE_alkalineValue is selected from following distribution：
kE_acidicMaximum be 1.15 × 107g/(m2·d)；
kE_acidicMinimum value or most probable value be 8.41 × 103g/(m2·d)；
kE_alkalineMaximum be 3.47 × 104g/(m2·d)；
kE_alkalineMinimum value or most probable value be 28.2g/ (m2·d)；
The migration situation to nucleic in glass solidified body course of dissolution is analyzed above, be can be seen that from analysis
Migration of the radionuclide in glass solidified body is occurred mainly in gel layer, and is diffused into waste Inter-packet gap from gel layer
In bulk solution, in view of the absorption, precipitation research to nucleic in gel layer understand not enough, in the migration of nucleic is calculated, this
Invention only calculates two kinds of extreme cases：
(1) whole release conditions, when glass solidified body dissolves, it is molten that the radionuclide for being contained all is discharged into main body
In liquid, this is the maximum of glass solidified body Radionuclide rate of release；
(2) part release conditions, when glass solidified body dissolves, it is assumed that the colloid for having same quality enters bulk solution
In, but nucleic is still inclusive in colloid, and only the nucleic in colloid pore water is discharged into bulk solution, and this is glass solidified body
The minimum of Radionuclide rate of release.
1) all release
When glass solidified body dissolving, if radionuclide all discharges, then the rate of release of radionuclide is：
RRN=rateG×S×IRN (5)
R in formulaRN：The release rate of radionuclide, g/day；
rateG：The dissolution rate of glass, g/ (m2·d)；
S:The glass surface area contacted with water, m2；
IRN：Radionuclide RN total amounts in glass, g (RN)/g (glass) (radiation included in i.e. every gram vitreum
The quality of property nucleic, g/g)；
Rate in formulaGCalculated using formula (3) or formula (4).
Glass and the initial contact surface area S of water0Calculating use following formula：
S0=fexposure×(2πr0 2+2πr0×L0) (6)
S in formula0：Glass includes the initial exposed surface area m in crack2；
r0It is the initial radium m of glass；
L0It is the initial length m of glass；
fexposureIt is the exposure factor.
Due in glass solidified body cooling procedure and other reasons produce heat and mechanical stress can cause glass solidification
Body produces crack in pouring can, and these cracks will cause water to enter inside glass in glass, so model must be closed in calculating
Reason determines the surface area contacted with water.The present invention illustrates glass and the surface area contacted uncertainty of water using the exposure factor,
The value for exposing the factor is general between 4-17, from empirically present invention selection minimum value.
China is high to put the standard size of the high-level waste tank proposed in conceptual design is：1.34m high, external diameter, 0.43m, wall
Thick 0.005m, the density of glass solidified body is 2690kg/m3。
Residual surface in glass degradation process by geometry specific surface area, the exposure factor and remaining glass quality
Multiplication is obtained.The expression formula is：
S=fexposure×SSP×(M0-∑M) (7)
S in formulaSP：Glass geometry specific surface area, object geometrical surface/mass of object；
M0:Glass solidified body initial mass；
∑M:Glass solidified body has dissolved quality.
At current time step end, the quality of glass degraded is calculated by following formula：
M (t)=rateG×t×S (8)
M (t) in formula：In the quality of current time step degraded,
S：In the surface area of current time step,
t：With the duration of the time step of speed identical time quantum.
In the remaining glass quality Σ M in current time step endtCalculated by following formula：
ΣMt=Σ Mt-1-M(t) (9)
Σ M in formulat-1：Remaining glass quality before current time step.Surface area for next time step passes through
Substitute Σ MtValue is calculated.
Parameter needed for model calculating is summarized and is shown in Table 1
The model of table 1 calculates required parameter value
2) part discharges
When glass solidified body dissolving, if it is assumed that radionuclide release in colloid pore water, also need to determine two parameters,
One is the concentration of radionuclide in pore water, radionuclide dissolving saturation in assuming pore water in this report, it is only necessary to
Obtain saturation data of the radionuclide in water；Second is the hole water content it needs to be determined that in colloid.
Table 2 lists the dissolubility data of part radionuclide in glass solidified body.
The dissolubility data of radionuclide in the glass solidified body of table 2
It is assumed that gel layer is exactly the whole erosion layer of glass solidified body, layer is corroded by grain shape and the dense matrix of thin mud shape
Clay crystallization is constituted, usually montmorillonitic clay.Referred to herein as pore water include clay platelet structure in interlayer water and
Water (non-structural water) between crystallization.Laboratory measures the quality hundred of the water corroded in layer formed on SRL131 glass samples
Divide content to be 7%, the erosion that high-level waste glass solidified body is formed under water or humid air is represented with this value in the present invention
The content of the pore water in layer.
The porosity of alterated layer is：
φ=XW×ρR/ρW (10)
In formula, φ：Corrode the porosity of layer；
XW：Corrode the mass fraction of layer reclaimed water；
ρR：Corrode the density of layer；
ρW：The density of hole reclaimed water.
Corrode the density of layer and without the value for determining, but be mainly clay minerals in layer by assuming to corrode, can be with
The amount of density and pore water according to clay mineral is represented.Be dehydrated clay mineral density representative value be：Kaolinite 2630kg/
m3, halloysite 2550kg/m3, nacrite 2600kg/m3.The density of usual POLARGEL NF is 2760kg/m3.These
It is worth the density (2600 to 2800kg/m in close proximity to high-level waste glass solidified body3), can be approximately considered clay crystallization
Granule density is identical with glass density.
Due to the presence of pore water, the density for corroding layer is different from the density of glass.Corrode the volume density ρ of layerRCan root
According to the density p that clay is crystallizedC, the density p of pore waterW, and porosity of hole when being occupied by the water completely be given：
Above formula substitutes into formula (10) and can obtain the expression formula of porosity and is：
φ={ 1+ (ρW/ρC)×[(1/XW)-1]}-1 (12)
The quality of dissolving ion in pore water is not considered, it is assumed that hole water density is pure water density,
By ρW=1000kg/m3, ρC=2690kg/m3And XW=0.07 substitution formula (12) can be calculated：
φ=0.17 (13)
Corroding the volume V of layer pore waterWCan be by the porosity φ and volume V of erosion layerRMultiplication is obtained：
VW=VR×φ (14)
The erosion layer volume that unit interval produces is replaced and can obtained with its quality and density：
VW=(M (t)/ρG)×φ (15)
By ρG=2690kg/m3And φ=17% is substituted into, and is obtained：
VW(m3)=6.3 × 10-5×M(t)(kg) (16)
Above-mentioned equation can be used for the volume for the unit of account time corroding layer reclaimed water, used as the letter of the amount of the glass degraded
Number.
The rate of release of so unit interval radionuclide is：
R'RN=VW×SORN (17)
R' in formulaRN：The minimum release rate of radionuclide, mol/day；
SORN：Radionuclide solubility mol/L.
3) nucleic decay is calculated
Model needs to consider the decay of nucleic that decay rate equation is as follows in calculating：
Mi(t)=Mi(0)e-λt (18)
M in formulai(t)：Nucleic i is in time t quality, g；
Mi(0)：The initial mass of nucleic i, g；
λ：Decay coefficient；
t：Decay time, s；
e：Natural logrithm.
The quality of nucleic t is iterated calculating in substituting into step iteration computing formula.
What document was given is typically all half-life data, so half-life period is converted to decay coefficient, decay coefficient by needs
With the mutual computing formula of half-life period：
T1/2=0.693/ λ (19)
T in formula1/2：Half-life period, s.
The computing formula of radioactive activity：
In formula, Ai(t)：Nucleic i is in time t activity, Bq；
Ni(t)：Nucleic i is in time t atomicity；
In known initial activity, it is also possible to which following formula is calculated：
Ai(t)=Ai(0)e-λt (21)
In formula, Ai(0)：Nucleic i is in initial time activity, Bq.
Known nucildic mass, is converted to atomicity：
N in formulaA:Avogadro's number, 6.022 × 1023；
A:Nucleic atomic mass, g/mol；
W:Nucildic mass, g.
The conversion of known quality and radioactive activity：
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 belong to the scope of the claims in the present invention and its equivalent technology
Within, then the present invention is also intended to comprising these changes and modification.
Claims (6)
1. a kind of construction method of high-level waste glass solidified body nuclein migration hydrolysis kinetic model, it is characterised in that：
Set up following hydrolysis kinetic equation：
In formula,
rateG：The dissolution rate of glass, g/ (m2·d)；
Effective speed constant, is only dependent upon glass composition, and unit is quality/(the area time)；
η：On H+ reactions to series, dimensionless；
Ea：The activation energy of ratedeterming step, kJ/mol；
R:Gas constant, 8.314J/ (molK)；
T:Temperature, K；
Q:Silicic acid concentration in solution, mass/volume；
K：The apparent silicic acid saturated concentration of glass, mass/volume；
klong：Long-term dissolution rate, quality/(area time)；
The dissolution rate of the glass obtained according to above hydrolysis kinetic equation, calculates radionuclide under two kinds of extreme cases
Rate of release：
(1) whole release conditions, when glass solidified body dissolves, the radionuclide for being contained all is discharged into bulk solution
In, this is the maximum of radionuclide rate of release in glass solidified body；
(2) part release conditions, when glass solidified body dissolves, are set with the colloid of same quality and enter in bulk solution, but
Nucleic is still inclusive in colloid, and only the nucleic in colloid pore water is discharged into bulk solution, this be glass solidified body in put
The minimum of penetrating property nucleic rate of release.
2. the structure side of high-level waste glass solidified body nuclein migration hydrolysis kinetic model as claimed in claim 1
Method, it is characterised in that：Also include being reduced to the hydrolysis kinetic equation set up：
Wherein, kEValue need to consider glass composition influence, including waste content inhomogeneities, the influence of solution composition, with
And the acid-base property of solution, carry out different values；η and EaAcid-base property according to solution carries out value：
For acid solution：
kE_acidicMaximum be 1.15 × 107g/(m2D),
kE_acidicMinimum value or most probable value be 8.41 × 103g/(m2D),
η=- 0.49,
Ea=31kJ/mol；
For alkaline solution：
kE_alkalineMaximum be 3.47 × 104g/(m2D),
kE_alkalineMinimum value or most probable value be 28.2g/ (m2D),
η=0.49,
Ea=69kJ/mol.
3. the structure of high-level waste glass solidified body nuclein migration hydrolysis kinetic model as claimed in claim 1 or 2
Method, it is characterised in that：When radionuclide all discharges, radionuclide rate of release is：
RRN=rateG×S×IRN
In formula,
RRN：The rate of release of radionuclide, g/day；
rateG：The dissolution rate of glass, g/ (m2·d)；
S:The glass surface area contacted with water, m2；
IRN：Radionuclide RN total amounts in glass, g (RN)/g (glass)；
Wherein, the surface area S that glass is initially contacted with water0Calculating use following formula：
S0=fexposure×(2πr0 2+2πr0×L0)
In formula,
S0：Glass includes the initial exposed surface area in crack, m2；
r0：The initial radium of glass, m；
L0：The initial length of glass, m；
fexposureIt is the exposure factor, value is 4-17；
Residual surface S (glass surface area for being contacted with water) in glass degradation process is：
S=fexposure×SSP×(M0-∑M)
In formula,
SSP：Glass geometry specific surface area, object geometrical surface/mass of object；
M0:Glass solidified body initial mass；
∑M:Glass solidified body has dissolved quality；
At current time step end, the quality of glass degraded is calculated by following formula：
M (t)=rateG×t×S
In formula,
M(t)：In the quality of current time step end glass degraded；
S：In the glass residual surface of current time step；
t：With the duration of the time step of speed identical time quantum；
In the remaining glass quality Σ M in current time step endtCalculated by following formula：
ΣMt=Σ Mt-1-M(t)
In formula,
ΣMt-1：Remaining glass quality before current time step.
4. the structure of high-level waste glass solidified body nuclein migration hydrolysis kinetic model as claimed in claim 1 or 2
Method, it is characterised in that：When radionuclide part discharges, radionuclide rate of release is：
R'RN=VW×SORN
In formula,
R'RN：The minimum release rate of radionuclide, mol/day；
VW：Corrode the volume of layer pore water, m3；
SORN：Radionuclide solubility, mol/L；
Corrode the volume V of layer pore waterWObtained by following formula：
VW=VR×φ
In formula,
VR：Corrode the volume of layer；
φ：The porosity of alterated layer.
5. the structure side of high-level waste glass solidified body nuclein migration hydrolysis kinetic model as claimed in claim 4
Method, it is characterised in that：The porosity φ of described alterated layer is：
φ=XW×ρR/ρW
In formula,
φ：Corrode the porosity of layer；
XW：Corrode the mass fraction of layer reclaimed water；
ρR：Corrode the density of layer；
ρW：The density of hole reclaimed water；
Corrode the density p of layerRThe density p that can be crystallized according to clayC, the density p of pore waterW, and hole when being occupied by the water completely
PorosityBe given：
6. the structure side of high-level waste glass solidified body nuclein migration hydrolysis kinetic model as claimed in claim 3
Method, it is characterised in that：It is also contemplated that the decay of nucleic, decay rate equation is as follows：
Mi(t)=Mi(0)e-λt
In formula,
Mi(t)：Nucleic i is in time t quality, g；
Mi(0)：The initial mass of nucleic i, g；
λ：Decay coefficient；
t：Decay time, s；
e：Natural logrithm.
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