Tritium accumulation and preservation into clay minerals for environmental protection
The comparative analysis of new and previously received data is represented, which allows us to estimate the influence of hydrodynamic conditions on tritium accumulation and retention in clay minerals. We have received time dependence of the tritium exchange process with the hydrogen of natural cl...
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
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irk-123456789-805582015-04-19T03:02:12Z Tritium accumulation and preservation into clay minerals for environmental protection Kartashov, V.V. Kovalenko, G.D. Letuchi, A.N. Samodurov, V.P. Vitko, V.I. Применение ядерных методов The comparative analysis of new and previously received data is represented, which allows us to estimate the influence of hydrodynamic conditions on tritium accumulation and retention in clay minerals. We have received time dependence of the tritium exchange process with the hydrogen of natural clay mineral matrix, long time halfcycle tritium capture by clay, the part of total tritium activity captured by clay for long time (more then 1 year). The received data and mathematical modeling let us determine the mineral component of natural clay, which more efficiently captures and retains tritium and is the best component for making barrier near radioactive tritium waste repository. Представлено порівняльний аналіз нових і раніше отриманих даних, що дозволив нам оцінити вплив гідродинамічних умов на нагромадження й утримання тритію в глинистих мінералах. Нами отримано часову залежність процесу обміну тритію з воднем природної матриці глинистих мінералів, оцінено тривалий напівперіод захоплення тритію природною глиною, частина повної активності тритію, що захоплюється на тривалий час (більш 1 року). Отримані дані і математичне моделювання дозволили нам визначити мінерал природної глини, що найбільше ефективно захоплює й утримує тритій, і є найкращим матеріалом для створення бар'єра навколо сховищ радіоактивного тритію. Представлен сравнительный анализ новых и ранее полученных данных, который позволил нам оценить влияние гидродинамических условий на накопление и удержание трития в глинистых минералах. Нами получена временная зависимость процесса обмена трития с водородом естественной матрицы глинистых минералов, оценен длительный полупериод захвата трития естественной глиной, часть полной активности трития, захватывающейся на длительное время (более 1 года). Полученные данные и математическое моделирование позволили нам определить минерал естественной глины, который наиболее эффективно захватывает и удерживает тритий, и является наилучшим материалом для создания барьера вокруг хранилищ радиоактивного трития. 2004 Article Tritium accumulation and preservation into clay minerals for environmental protection / V.V. Kartashov, G.D. Kovalenko, A.N. Letuchi, V.P. Samodurov, V.I. Vitko // Вопросы атомной науки и техники. — 2004. — № 5. — С. 103-107. — Бібліогр.: 8 назв. — англ. 1562-6016 PACS: 28.41.Kw, 28.41.Te, 89.60.+x http://dspace.nbuv.gov.ua/handle/123456789/80558 en Вопросы атомной науки и техники Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine |
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English |
| topic |
Применение ядерных методов Применение ядерных методов |
| spellingShingle |
Применение ядерных методов Применение ядерных методов Kartashov, V.V. Kovalenko, G.D. Letuchi, A.N. Samodurov, V.P. Vitko, V.I. Tritium accumulation and preservation into clay minerals for environmental protection Вопросы атомной науки и техники |
| description |
The comparative analysis of new and previously received data is represented, which allows us to estimate the
influence of hydrodynamic conditions on tritium accumulation and retention in clay minerals. We have received
time dependence of the tritium exchange process with the hydrogen of natural clay mineral matrix, long time halfcycle tritium capture by clay, the part of total tritium activity captured by clay for long time (more then 1 year). The
received data and mathematical modeling let us determine the mineral component of natural clay, which more
efficiently captures and retains tritium and is the best component for making barrier near radioactive tritium waste
repository. |
| format |
Article |
| author |
Kartashov, V.V. Kovalenko, G.D. Letuchi, A.N. Samodurov, V.P. Vitko, V.I. |
| author_facet |
Kartashov, V.V. Kovalenko, G.D. Letuchi, A.N. Samodurov, V.P. Vitko, V.I. |
| author_sort |
Kartashov, V.V. |
| title |
Tritium accumulation and preservation into clay minerals for environmental protection |
| title_short |
Tritium accumulation and preservation into clay minerals for environmental protection |
| title_full |
Tritium accumulation and preservation into clay minerals for environmental protection |
| title_fullStr |
Tritium accumulation and preservation into clay minerals for environmental protection |
| title_full_unstemmed |
Tritium accumulation and preservation into clay minerals for environmental protection |
| title_sort |
tritium accumulation and preservation into clay minerals for environmental protection |
| publisher |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| publishDate |
2004 |
| topic_facet |
Применение ядерных методов |
| url |
http://dspace.nbuv.gov.ua/handle/123456789/80558 |
| citation_txt |
Tritium accumulation and preservation into clay minerals for environmental protection / V.V. Kartashov, G.D. Kovalenko, A.N. Letuchi, V.P. Samodurov, V.I. Vitko // Вопросы атомной науки и техники. — 2004. — № 5. — С. 103-107. — Бібліогр.: 8 назв. — англ. |
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Вопросы атомной науки и техники |
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| fulltext |
TRITIUM ACCUMULATION AND PRESERVATION INTO CLAY
MINERALS FOR ENVIRONMENTAL PROTECTION
V.V. Kartashov1, G.D. Kovalenko1, A.N. Letuchi1, V.P. Samodurov2, V.I. Vitko1
1Ukrainian Scientific Research Institute of Ecological Problems, Kharkov, Ukraine
e-mail: rsrm@niiep.kharkov.ua
2Institute of Geological Sciences, Minsk, Belarus
e-mail: samod@ns.igs.ac.by
The comparative analysis of new and previously received data is represented, which allows us to estimate the
influence of hydrodynamic conditions on tritium accumulation and retention in clay minerals. We have received
time dependence of the tritium exchange process with the hydrogen of natural clay mineral matrix, long time half-
cycle tritium capture by clay, the part of total tritium activity captured by clay for long time (more then 1 year). The
received data and mathematical modeling let us determine the mineral component of natural clay, which more
efficiently captures and retains tritium and is the best component for making barrier near radioactive tritium waste
repository.
PACS: 28.41.Kw, 28.41.Te, 89.60.+x
1. INTRODUCTION
Tritium is one of the most hazardous β-emitters. Its
large amounts are contained both in the cooling water of
nuclear reactors and settling basins, radioactive waste
repositories (RWR) and it can escape into the
environment in the case of leakages. Tritium was
identified in a study by the Nuclear Energy Agency of
the Organization for Economic Co-operation and
Development as one of four volatile radionuclides
arising from the nuclear fuel cycle with potential long
term radiological significance. The environmental
behaviour of tritium was addressed in the symposium
[1]. Tritium was registered in deep ground water at the
areas affected by Nuclear Power Plants [2].
Tritium was detected in water sampled at
groundwater-monitoring points located at the Kharkov
and Kiev RWRs [3,4]. In [3,5,6] we investigated some
aspects of Kharkov' accident.
Tritium exchanges with hydrogen of clay structure
during its distribution through clay layers. This process
can lead to decrease of tritium activity after such layers.
The review of isotopic exchange of tritium with
hydrogen in clay was published recently [7].
The isotopic exchange of tritium with hydrogen,
included in free water, pore and interlayer water, was
researched in laboratory experiments. These processes
last 1…100 days. Investigation of an isotopic exchange
of tritium with hydrogen, which is included in
OH-groups of clay structure, is going on more than
1 year. We have studied this process as a leatning result
of tritium distribution in the environment after the
radiation accident on Kharkov RWR since 1997.
The received data and mathematical modeling let us
determine the mineral component of natural clay, which
more efficiently captures and retains tritium, and is the
best component for making barrier near radioactive
tritium waste repository.
2. GEOLOGICAL ENVIRONMENT
PARAMETERS MEASUREMENTS
In immediate proximity from radioactive waste
repositories of Kharkov RWR, from which there was a
leakage of tritium, the borehole 31d was drilled and soil
was sampled on different depths. As it was clarified
after the mineralogical analysis, the underlayers mainly
consist of loams containing much clay. The chemical
and mineralogical composition of an aeration zone was
defined.
2.1. Chemical composition of aeration zone soils
SiO2 predominates in soils (72…76%), whereas
compounds of aluminium and ferric oxides are ~10%
and ~5% accordingly. The oxides of kalium,
magnesium and calcium are contained in concentrations
of about 1.5%. The rest elements are in minor
impurities.
From data analysis it follows that the soil is
introduced by an intermixture of quartz sand and clay
minerals. Thus, hydromica (illite) cannot be a layer-
making mineral in clay. So, the contents of kalium is
low. Therefore heightened contents of potash feldspars
in a sand fraction (up to 13% К2О in potash feldspars)
and illite (5…10 % К2О) in a clay fraction are not
registered. Another feature of clay minerals composition
corresponds to the rather low content of aluminium,
therefore kaolinite, in which one Al2O3 compounds are
39.5%, is an impurity, and does not predominate among
clays.
2.2. Mineralogical composition of aeration zone soils
PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. 2004, № 5.
Series: Nuclear Physics Investigations (44), p. 103-107. 103
The sand fraction is presented by light (quartz) sand.
Soils clayiness varies from 30 to 70%.
The quartz is determined on jerks 4.24, 3.34, 2.45 Å
on diffractograms. The feldspar is registered in minor
impurities and is revealed in the field of 3.2 Å. The
calcite in samples is legibly seen on jerk 3.03 Å.
The quartz predominates in sand fraction
composition. The minor impurity of feldspars is
registered, and the impurity of a calcite is registered in
samples. The percentage of a calcite is determined
under the chemical analysis (5.7%).
Common soil type in a section is the following: the
sand-clay materials predominate. Various parts of the
section differ by essential common clayiness
oscillations and by concentrations of separate clay
components. Clayiness predominates (50…60%) in the
upper part of the section (1…5 м). The essential
clayiness oscillations (10…40%) are registered below in
the section.
Three basic types of clay minerals are registered:
montmorillonite, kaolinite and illite. Illite is registred
only as impurities. The section can be divided into 3
parts: upper (1…9 м) and lower (12.5…20.1 м) with a
dominance of montmorillonite, and middle (11…
12.5 м) is essentially kaolinite.
The weighted mean values of clay minerals (depths
1.2…20.1 m) are the following: clay – 34.2%;
montmorillonite – 21.9%; illite – 3.2%; kaolinite-9.5%.
3. VOLUMETRIC TRITIUM ACTIVITY IN
BOUND WATER ON VARIOUS DEPTHS
The differential-thermal analysis (DTA) was held
for three samples. The intervals of temperatures, at
which different types of water are separated, were
defined. The measurements of volumetric tritium
activity in water on different depths are held in four
fractions: 1st fraction is the free water extracted at
temperatures up to 105 °С; 2nd fraction is the bound
water extracted at temperatures from 105 °С up to
250 °С; 3rd fraction is the bound water extracted at
temperatures from 250 °С up to 400 °С; 4th fraction is
the bound water extracted at temperatures from 400 °С
up to 800 °С. The selection of free and bound water was
carried out with two methods: the heating up selection
method and the pressure method. Both methods have
yielded similar results, showing that the heating up does
not influence on the water activity in the different
fractions.
The measurement results of tritium activity in all
fractions are represented in Fig. 1. The figure represents
the dependence of volumetric tritium activity in the
indicated fractions from the depth in the borehole 31d.
Analyzing data, represented in Fig. 1, it is necessary
to note, that on depths more than 6 m the volumetric
tritium activity in all fractions is approximately equal
within errors of measurement. On these depths the time
of tritium interaction with clay minerals exceeds 10
years, therefore the volumetric activity in all fractions
are equal due to the isotopic exchange. The exception
from this one can see on the depths up to 6 m. The time
of tritium interaction with clay minerals on these depths
was less than 2 years, therefore the volumetric tritium
activity were not equal in all fractions due to the
isotopic exchange. On these depths the maximum
tritium activity is in free water, and the minimum is in
crystalline water. In few years the maximum on depth
4 m will move deeper into the aeration zone, and the
activity in all fractions will be aligned.
Fig. 1. Volumetric tritium activity vs depth
4. TRITIUM PROPAGATION THROUGH
THE AERATION ZONE
The process of tritium propagation through aeration
zone was studied theoretically as well as by
environment measurements.
4.1. Model of tritium transport through an aeration
zone
The calculated tritium activity in free water is found
as the solution of the differential equation in particular
derivatives, described the tritium transport process
through the aeration zone [8]:
=
+⋅⋅β−⋅⋅α
−⋅υ−⋅++⋅=⋅
00 ),z,y,x(C
)t,z,y,x(fCnCn
CCD)CC(DCn zzzyyxxmt
(1)
where x, y z, t are the spatial coordinates and time, x, y
are the plane ground coordinates, z>0 is the depth, the
coordinates' centre is arranged on the ground; C(x,y,z,t)
is the tritium volumetric activity in the point with
coordinates x, y, z, t; Сt=∂C/∂t is the volumetric
activity's derivative on time; Cxx=∂2C/∂x2 is the
volumetric activity's second derivative on x; Cyy=∂2C/∂
y2 is the volumetric activity's second derivative on y; Cz,
Czz=∂C/∂z, ∂2C/∂z2 are the volumetric activity's first and
second derivative on z; n is active soil porosity; Dm is
the molecular diffusion coefficient in soil; D is the total
molecular diffusion and hydrodynamics coefficient; υ is
the filtration velocity, directing along the vertical axis z;
α is the tritium radioactive decay constant; f(x,y,z,t) is
an external tritium source. The time dependence
f(x,y,z,t) consists of two components, relevant to two
radioactive waste repositories (units №19,20), with own
time dependencies. The dependence from coordinates
was set by polygon enveloping the total repositories
104
area. Total release from unit № 19 is 166 Ci, from unit
№ 20 is 944 Ci. We describe the tritium capture by clay
structure by adding to the right part of the eq. (1) the
term -β⋅n⋅C, similar to the term describing a radioactive
decay. The coefficient β relates to the halftime (T) of
tritium capture by clay structure as follows: β=δ⋅ln(2)/T,
where δ is the part of tritium, captured by clay structure.
To define some dynamic parameters of tritium
distribution in the aeration zone we have drilled two
boreholes 31н and 31d. The tritium activity was defined
in free water in samples selected on different depths.
The borehole 31d was drilled 3.5 years after borehole
31н on distance approximately 1 m from it.
4.2. Measurement results
The measurement results of the volumetric tritium
activity in the aeration zone in boreholes 31н and 31d
are displayed in Fig. 2. Calculated curves 1 and 2 in
Fig. 2 represent the dependence of activity from depth
for these boreholes accordingly.
Fig. 2. Tritium activity depth dependence in free water
for boreholes 31н and 31d
Curve 2 is gauged in 3.5 years after curve 1. For
these years the central maximum at 11.5 m was shifted
to the depth of 16 m, and the quantity in the maximum
has decreased. The measured quantities are shown with
measurement errors. The influence of activity capillary
lift from aquifer we describe by the function:
F(z) = A0 · exp (1.3 · (z-z0) ) , z < z0 (2)
Where А0 is the tritium volumetric activity in aquifer; z
is the depth; z0 is the depth of the aquifer surface; 1.3 is
empirical coefficient. This function is added to solution
of Eq. (1) to describe the capillary lift on depths beneath
17 m. We show the necessity of introducing this
function in [5]. The activity in aquifer (А0 coefficient in
Eq. (2)) is decreased in time not only due to radioactive
decay, but also due to activity flow into aquiclude.
Curve 2 shows activity peak on depths 2…7 m with
maximum on 4 m. This peak was found in
measurements and is described by the solution of eq. (1)
with the additional tritium leakage in time 2…3 years
prior to measurements. The quantity of leakage is
selected to get coincidence of measured and calculated
values. This maximum it is not visible on curve 1 for
borehole 31н. Obviously, the tritium leakage has taken
place after sampling from borehole 31н. The solution of
Eq. (1) for the borehole 31н was normalized on the
measurement values. This normalization was utilized
for depth-dependence calculations of tritium activity in
the close located borehole 31d for later time. In
calculations for the borehole 31d the unknown
parameters δ and Т from Eq. (1) were used only. By the
selection of these parameters we have described the
depth dependence of tritium activity in the borehole 31d
very well. It has appeared, that the value of activity,
which is captured by clay structure for long time due to
the isotopic exchange for our conditions, is equal to 7%
(parameter δ=0.07). And the halftime of tritium capture
Т is equal to 2 years.
5. TIME DEPENDENCE PROCESSES OF
TRITIUM CAPTURE BY CLAY
STRUCTURE
As the velocity of tritiated water in the aeration zone
approximately is equal to 1 m/year and the width of a
maximum is about 5 m, the interaction time of tritiated
water with clay is about 5 years. At this time, as a result
of an ion exchange, tritium substitutes hydrogen in clay
mineral structure, including the closely coupled
crystalline water, get free at high heat from OH-groups
of clay minerals [7]. In vivo measurements demonstrate,
that at that interaction time small tritium activity is
captured by clay with halftime period of capture
approximately equal to 2 years. Our laboratory measure-
ments demonstrate, that the large tritium activity is
captured and is held by structure about 10 days.
Therefore time dependence process of tritium
capture by clay structure is possible to describe
mathematically by two exponential dependences, for
7% of activity half-period of capture approximately
equals to 2 years, and for 93% of activity it is about
10 day, see Fig. 3.
Fig. 3. Time parameters of washing out curve for
natural clays of Kharkov radioactive waste repository
Curve 1 in Fig. 3 describes common time
dependence of tritium activity decrease in clay during
outwashing by distilled water, curve 2 is the component
of outwashing with the small period, and curve 3 is the
component with large period. In 50 days of outwashing
by distilled water in laboratory there is approximately
7% of activity remained. We assume that times for both
processes of capture and washing out are equal. The part
of activity with large period of capture in our conditions
approximately equals to 7%. From our point of view,
105
this process is determined by "deep" tritium capture by
OH-groups (crystalline water). The crystalline water in
relation to free water for our clays makes up about 15%.
And on our data 7% of crystalline water is captured and
is preserved about 2 years. From this data it is clear, that
about half of crystalline water is captured and held
tritium due to the isotopic exchange on prolonged time.
If to consider, that the part of crystalline water that
capture and held tritium on time ~2 years in kaolinite
and montmorillonite approximately equal, then for
creation of a clay barrier on path of tritium penetration
into an environment most preferential is such
combination of clay materials, in which crystalline
water is more, and, in particular, therefore kaolinite clay
layer is much more preferential then montmorillonite
one.
6. CLAY TYPE INFLUENCE ON TRITIUM
PASSING THROUGH AERATION ZONE
As defined above the average content of
montmorillonite in the natural clays in region of
Kharkov radioactive waste repository is equal to 21.9%,
and kaolinite is equal to 9.5%. Accepting, that
montmorillonite contains 3% of crystalline water, and
kaolinite contains 14%, we obtain, that the average
crystalline water contents in the aeration zone near
Kharkov RWR is equal to 11.7%. And on our model
estimations from this crystalline water 7% are captured
and held for ~2 years.
If to consider, that the parts of crystalline water that
captures and helds tritium on time ~2 years in kaolinite
and montmorillonite are approximately equal, then we
can suppose, that if all clay has only montmorillonite,
then it captures and holds 3.3% of crystal water for
~2 years, and if all clay has only kaolinite, this part
would be 15.4%.
Thus, for the parameter δ in Eq. (1) we have three
values: δ=0.07 for natural clay near Kharkov RWR;
δ=0.033 for hypothetical clay from pure
montmorillonite; δ=0.154 for hypothetical clay from
pure kaolinite. Solving Eq. (1) for different values δ and
calculating the tritium flow on boundary of clays, we
obtain different time dependences of common tritium
activity, which it is going out from the aeration zone
(thickness of natural clays ~17 м). This tritium is
accumulated in the aquifer and the aquifuge. The results
of calculations are displayed in Fig. 4. In this figure
three calculated curves and measurement points with
errors of measurements are displayed. The measurement
values are obtained as a volume integral on all stratums
of aquifer and an aquifuge on boundary of which
volumetric activity of tritium decreased on 3-4 degree as
compared to maximum values. Volumetric tritium
activity is measured in water of 23 boreholes. The
details of calculations see in [5].
The calculations demonstrate, what total tritium
activity after the layer with width 17 m, consisted of
natural clays in vicinity of Kharkov RWR will be. The
curve 1 demonstrates how tritium is passing through a
barrier of natural clays. Curve 2 demonstrates how
tritium will pass through hypothetic pure
montmorillonite clay layer and curve 3 demonstrates
similar results for hypothetic pure kaolinite clay layer.
Fig. 4. Total tritium activity after aeration zone: 1-
natural clay layer, 2-pure montmorillonite clay layer
(hypothetic), 3-pure kaolinite clay layer(hypothetic)
The value in the maximum for a curve 2 is equal to
39.3 Ci, and that for the curve 3 is 22.2 Ci. As we see,
behind the kaolinite clay layer maximum tritium activity
approximately in 2 times less, than behind the similar
montmorillonite clay layer. Taking into account, that
the aeration zone contains only 34.2% of clays, the
same results can be received for approximately three
times less clay layer composed of pure clay.
As it follows from this data, the kaolinite clay is
much more effective then montmorillonite clay as a
barrier on tritium propagation into an environment.
Therefore building the natural barriers on tritium
propagation into an environment it is necessary to use
the kaolinite clay. Capture and reduction of tritium
activity due to a radioactive decay provide an effective
barrier. These conclusions are related to a barrier, which
tritium is passing more then 2 years for more effective
isotopic exchange with hydrogen of crystalline water.
Creating the artificial barriers reducing tritium
propagation into an environment it is necessary to
provide presence in its clay structure strongly bound
hydrogen groups and to provide small filtration velocity
through such barriers. And the time of an isotopic
exchange with such groups great enough and should be
comparable to the period of tritium radioactive decay.
CONCLUSIONS
The data on tritium outwashing from natural clays
by the distilled water and results of tritium distribution
in the aeration zone let us obtain a time dependence of
tritium capture in wide time range. We have found, that
for natural clays near Kharkov RWR the value of
common tritium activity captured by the clays on time
about 2 years and more reaches 7%.
Is was shown, that for creation of a clay barrier on
path of tritium penetration into an environment the most
preferential is such combination of clay materials, in
which it is more crystalline water, and, in particular,
106
therefore kaolinite clay layer is much more preferential
that montmorillonite one.
Thus, the clay minerals as a result of tritium capture
by OH-groups strengthen the protective characteristics
of a barrier enclosing radioactive waste repository with
tritium if passing times of tritium through them is more
than 2 years. The efficiency of this protective barrier is
more, when a barrier has more strongly bound
OH-groups.
Work is executed with the INTAS financial support,
project INTAS-01-2166.
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the Symp. San Francisco, 1978. IAEA, Vienna, 1979,
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НАКОПЛЕНИЕ И УДЕРЖАНИЕ ТРИТИЯ ГЛИНИСТЫМИ МИНЕРАЛАМИ ДЛЯ ЦЕЛЕЙ
ОХРАНЫ ОКРУЖАЮЩЕЙ СРЕДЫ
В.В. Карташов, Г.Д. Коваленко, А.Н. Летучий, В.П. Самодуров, В.И. Витько
Представлен сравнительный анализ новых и ранее полученных данных, который позволил нам оценить
влияние гидродинамических условий на накопление и удержание трития в глинистых минералах. Нами
получена временная зависимость процесса обмена трития с водородом естественной матрицы глинистых
минералов, оценен длительный полупериод захвата трития естественной глиной, часть полной активности
трития, захватывающейся на длительное время (более 1 года). Полученные данные и математическое
моделирование позволили нам определить минерал естественной глины, который наиболее эффективно
захватывает и удерживает тритий, и является наилучшим материалом для создания барьера вокруг
хранилищ радиоактивного трития.
НАГРОМАДЖЕННЯ ТА УТРИМАННЯ ТРИТІЮ ГЛИНИСТИМИ МІНЕРАЛАМИ З МЕТОЮ
ОХОРОНИ НАВКОЛИШНЬОГО СЕРЕДОВИЩА
В.В. Карташов, Г.Д. Коваленко, О.М. Летучий, В.П. Самодуров, В.І. Вітько
Представлено порівняльний аналіз нових і раніше отриманих даних, що дозволив нам оцінити вплив
гідродинамічних умов на нагромадження й утримання тритію в глинистих мінералах. Нами отримано часову
залежність процесу обміну тритію з воднем природної матриці глинистих мінералів, оцінено тривалий
напівперіод захоплення тритію природною глиною, частина повної активності тритію, що захоплюється на
тривалий час (більш 1 року). Отримані дані і математичне моделювання дозволили нам визначити мінерал
природної глини, що найбільше ефективно захоплює й утримує тритій, і є найкращим матеріалом для
створення бар'єра навколо сховищ радіоактивного тритію.
107
1Ukrainian Scientific Research Institute of Ecological Problems, Kharkov, Ukraine
e-mail: samod@ns.igs.ac.by
PACS: 28.41.Kw, 28.41.Te, 89.60.+x
ConclusionS
REFERENCES
В.В. Карташов, Г.Д. Коваленко, А.Н. Летучий, В.П. Самодуров, В.И. Витько
В.В. Карташов, Г.Д. Коваленко, О.М. Летучий, В.П. Самодуров, В.І. Вітько
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