Upload
gang
View
218
Download
0
Embed Size (px)
Citation preview
Accepted Manuscript
Molecular dynamical study of physical properties of (U0.75Pu0.25)O2-x
J.J. Ma, J.J. Zheng, M.J. Wan, J.G. Du, J.W. Yang, G. Jiang
PII: S0022-3115(14)00275-X
DOI: http://dx.doi.org/10.1016/j.jnucmat.2014.05.008
Reference: NUMA 48133
To appear in: Journal of Nuclear Materials
Received Date: 29 October 2013
Accepted Date: 3 May 2014
Please cite this article as: J.J. Ma, J.J. Zheng, M.J. Wan, J.G. Du, J.W. Yang, G. Jiang, Molecular dynamical study
of physical properties of (U0.75Pu0.25)O2-x , Journal of Nuclear Materials (2014), doi: http://dx.doi.org/10.1016/
j.jnucmat.2014.05.008
This is a PDF file of an unedited manuscript that has been accepted for publication. As a service to our customers
we are providing this early version of the manuscript. The manuscript will undergo copyediting, typesetting, and
review of the resulting proof before it is published in its final form. Please note that during the production process
errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal pertain.
Molecular dynamical study of physical properties of(U0.75Pu0.25)O2−x
J.J.Maa, J.J.Zhengb, M.J.Wana, J.G.Duc, J.W.Yanga, G.Jianga,∗
aInstitute of Atomic and Molecular Physics Sichuan University, Chengdu 610065, ChinabInstitude of Theoretical Physics and Department of Physics, Shanxi University, Taiyuan
030006, ChinacCollege of Physical Science and Technology, Sichuan University, Chengdu 610064, China
Abstract
Physical properties of mixed-oxide fuel (U0.75Pu0.25)O2−x (x =0.0, 0.02, 0.06,
0.1, 0.15, 0.2, 0.25) have been investigated by the molecular dynamic (MD)
simulation in the temperature range 300-3000K. The lattice parameter, lin-
ear thermal expansion coefficient, compressibility, bulk modulus and thermal
conductivity are systematically investigated and analyzed by comparison with
experiments and previous calculations. The calculated results of physical prop-
erty are in good agreement with the experimental values and literature data.
The oxygen vacancies have a significant effect on thermal properties of MOX.
As oxygen vacancies increase, the bulk modulus gradually tend to be linear rela-
tionship with temperature and the thermal conductivity decreases very clearly,
also, the temperature dependence weakens. In addition, we found that the in-
fluence of plutonium concentration for thermal conductivity is so small that it
can be ignored when oxygen vacancies are existent.
1. Introduction
Uranium-plutonium mixed oxide fuel (MOX) is regarded as an important
candidate in the energy resources due to the effective utilization rate of nuclear
∗Corresponding author. Tel./fax: +86 28 85408810.Email address: [email protected] (G.Jiang)
Preprint submitted to Journal of Nuclear Materials May 12, 2014
fuel and significant function to protect the environment in the process of dis-
posing nuclear waste. At the moment, the MOX-fuel have been loaded into5
the commercial light water reactor (LWRs. (U, Pu)O2 contained high Pu con-
centrations (15 − 30%) will be widely used in the fast breeder reactors (FBR)
or transmutation rectors in future [1, 2, 3, 4, 5, 6]. In order to operate and
develop the nuclear reactor system safely, it is crucial to forecast the physical
properties of MOX-fuel [7], especially, the understanding of thermal expansion10
and thermal conductivity which is avail to design installation of nuclear fuel.
These properties of MOX have been studied extensively in the past, such as
thermal conductivity.
Gibby et al. [8] comprehensively investigated the thermal conductivity of
(U,Pu)O2 containing up to 30% PuO2 and established the basic approaches15
to measure the characterizations of nuclear fuel. It was found that the ther-
mal conductivity of (U,Pu)O2 had a small but systematical decrease with in-
creasing of Pu content. Philipponneau [4] developed an equation for FR-MOX
fuel by reviewing the previous results and studying the thermal conductivity
of (U,Pu)O2−x mixed oxide fuel. He recommended to neglect the effect of the20
amount of plutonium on thermal conductivity in high Pu concentration range
and observed that the decrease of conductivity is due to a decrease of the O/M
(i.e. O/(U+Pu)) ratio. Duriez et al. [2] preformed an experimental measure-
ment of the thermal conductivity of low Pu content (U1−yPuy)O2−x mixed
oxides in the ranges 0.03 ≤y≤ 0.15 and 1.95 ≤x≤ 2.00. Through the compari-25
son with high plutonium content FBR fuel, they proposed that the effect of the
O/M radio should be taken into account when predicting thermal conductivity
of mixed oxide fuels.
Due to fluctuations of O/M ratio in experiments, these results are not ac-
curate to describe the effect of oxygen-to-metal radio. With the development30
of computer simulation techniques, molecular dynamics (MD) can be a useful
technique to obtain the information of oxide fuels in recent years. The phys-
ical properties of UO2 [9, 10, 11], PuO2 [12], UO2−x [13], PuO2−x [7, 14],
and (U,Pu)O2 [15] have been evaluated over a wide temperature, above room
2
temperature, the calculated results are almost in agree with the experimental35
values. Arima et al. [1] have performed MD simulations of hypostoichiometric
MOX-fuel U0.8Pu0.2O2−x (x = 0.0 − 0.06) solid solutions in the temperature
range from 300 to 2000K. Their MD simulation results indicate that the oxy-
gen deficiency x has a larger effect on the thermal conductivity. However, their
simulation just in a small temperature (300 − 2000K) and oxygen deficiency40
(0.0− 0.06) range, there is still no reliable conclusion about the effect of oxygen
vacancy on the physical properties of MOX. In present work, the MD simula-
tion of mixed oxide fuel, (U0.75Pu0.25)O2−x (x=0.0, 0.02,0.06,0.1,0.15,0.20,0.25),
has been performed to evaluate the lattice parameter, linear thermal expan-
sion, compressibility, bulk modulus and thermal conductivity in temperature45
range 300− 3000K. In order to ensure the influence of high Pu content on ther-
mal conductivity of MOX, we further investigated the thermal conductivity of
U1−xPuxO2 (x = 0.15, 0.2, 025, 0.3) and compared the results with UO2 which
had been system systematically reported by Watanabe et al.[16, 17].
This paper is organized as follows: In Sec. II and III, we present a detail50
description of the MD simulation details and potential function, respectively.
The results are presented in Sec. IV. Here, we show our results and compare
with the available experimental and theoretical studies. Finally, we give our
main conclusions of physical properties of (U0.75Pu0.25)O2−x in Sec. V.
2. Simulation details55
The defects of U0.75Pu0.25O2 may be existed in oxygen vacancy or metal
clearance. To investigate physical properties between different ratios of the
defects, we selected defects in oxygen vacancy as initial model, so that the
same structure was kept in the case of different ratio. The MD calculation
for U0.75Pu0.25O2 was performed for a system of 6 × 6 × 6 supercell which in-60
cludes 2592 ions (864 cations and 1728 anions) as initial structure arranged in
a CaF2 type crystal structure. Fig. 1 presents the structure of unit cell of
U0.75Pu0.25O2−x. Based on the prefect structure of CaF2, the (U4+ ,Pu4+)
3
Figure 1: The unit cell of (U0.75Pu0.25)O2−x.
and O2− ions were arranged at each regular site of the CaF2 structure. One
atom of oxygen was taken out as deficiency which is showed by hollow circular65
in the picture. For the other MOX compositions included oxygen deficiency,
we take U0.75Pu0.25O2−x where x = 0.02 as example, first we remove small
amounts of oxygen ions as deficiency randomly in the initial structure, then
select the two +4 ions replaced with Pu3+ or U3+ near each oxygen vacancy
to preserve charge neutrality. The structure for each of the other composi-70
tion (x = 0.06, 0.1, 0.15, 0.2, 0.25) can be obtained in the same way, the only
difference is the number of oxygen vacancy which is decided by the O/M ra-
tio. In the present study, calculations are well performed by the Large-scale
Atomic/Molecular Massively Parallel Simulator (LAMMPS) program [18] using
the molecular dynamics (MD) technique.75
The calculations were carried out in the temperature range from 300 to
3000K, and in the pressure range from 0.1MPa to 1.5GPa. They were con-
trolled by the Nose/Hoover temperature thermostat and Nose/Hoover [19, 20]
4
pressure barostat, respectively. These techniques in the MD simulation were
performed under standard constant pressure-temperature (NPT) and constant80
volume-temperature (NVT) ensembles. Also, the calculations employed 3D pe-
riodic boundaries and performed 10000 steps equilibration run at expected tem-
perature and pressure. Although the number of steps is small, the equilibrium
of system is achieved as judged from the changes in the temperature (2.5%),
internal energy (0.05%), and volume (0.3%).85
For the simulation of thermal conductivity, direct method and the Green-
Kubo method are applied most commonly. Schelling et al [21] systematically
explored the strengths and weaknesses of two methods through a model of crys-
talline silicon. The result of comparison is that both methods were in reasonable
agreement with the experimental value and proved that either method can be90
applied to compute bulk thermal conductivity in perfect crystalline solids. In
addition, they gave an analysis of finite-size effects, which indicated that the
effects are much more severe in the direct method due to the presence of real
interfaces at heat source and sink. Based on the findings of their study, the
Green-Kubo approach is adopted for simulation of thermal conductivity in the95
present study. In order to sufficiently converge the current-current autocorre-
lation function, the program needs very long simulation times (5 × 105 steps).
During the simulation, the supercell shape was kept to cubic structure even for
the system including oxygen defect.
3. Potential functions100
In this work, we applied Born-Mayer-Huggins (BMH) potential with the
partially ionic model (PIM) to each ion pair in simulated crystals. This potential
function is given by [10]
UPIM =zizje
2
rij+ f0(bi + bj)exp
ai + aj − rij
ai + aj− cicj
r2ij
. (1)
Where rij is the distance between i and j atoms, f0 is the adjustable para-
meter which equals to 4.1860, ai , bi and ci were determined by experimental105
5
Table 1: Potential parameters for the BMH type with PIM.
Ion Zi ai bi ci
(67.5%) (A) (A) (eV0.5A3) Sources
O2− -1.35 1.847 0.166 1294 Ref.[22, 23]
U4+ 2.70 1.318 0.0306 0.0 Ref.[10]
Pu4+ 2.70 1.272 0.0325 0.0 Ref.[10]
U3+ 2.025 1.318 0.0306 0.0 Ref.[24]
Pu3+ 2.025 1.2217 0.0128 0.0 Ref.[1]
data. zi and zj are the effective partial electronic charges on the ith and jth
ions, and the ionic bonding of 67.5% is assumed for (U0.75Pu0.25)O2−x system.
The first term on the right side of Eq. (1) represents long-range Coulomb inter-
action, and the Coulomb interaction energy is considered by Ewalds simulation.
Other terms represent short-range interactions: the second term is the repulsive110
potential between ionic cores; the last one which is called Morse-type potential
[25] is the attractive part of the Van der Waals interaction. The parameters (a,
b and c) are listed in Table 1.
In present work, We use Pu3+ potential for smaller value of x (i.e. x =115
0.02, 0.06, 0.1), and added U3+ ions to (U0.75Pu 0.25)O2−x system when x =
0.15, 0.2, 0.25. In order to investigate the influence of the ratios of trivalent
ions (U3+/ Pu3+) on the simulation results, we compare the lattice constants
at x = 0.02 and x = 0.25 under the different U3+/Pu3+ ratios. The lat-
tice parameters as a function of temperature are shown in Fig. 2, in which120
symbols represent the MD results and lines are the data listed in literature.
It is also confirmed that changes in lattice constants (0.08%) are extremely
small under different U3+/Pu3+ ratio. The results demonstrate that the influ-
ence of the ratios (U3+/ Pu3+) on the lattice constants of (U0.75Pu0.25)O2−x
(x = 0.02, 0.06, 0.10, 0.15, 0.20.0.25) can be ignored.125
6
Figure 2: The lattice constants of (U0.75Pu0.25)O2−x (x = 0.02, 0.25) as a function of tem-
perature under different U3+/Pu3+ ratio, along with Arima’s [1] results of (U1−yPuy)O2(y =
0.2, 0.3).
7
Figure 3: Lattice constants calculated by MD simulations as a function of temperature for
(U0.75Pu0.25)O2−x(x =0.0, 0.02, 0.06, 0.1, 0.15, 0.2, 0.25).
4. Results and discussion
4.1. Lattice parameters
To our knowledge, the temperature and oxygen deficiency ranges are quite
limited due to experimental conditions [8, 2, 26], but the high-temperature and
high oxygen deficiency lattice constants can be obtained from the MD calcula-130
tion. The variation of the lattice parameters of U0.75Pu0.25O2−x(x =0.0, 0.02,
0.06, 0.1, 0.15, 0.2, 0.25) with temperature calculated by the MD method are
shown in Fig. 3, along with Arima’s [1] theoretical results for U0.8Pu0.2O2−x
(x = 0.02 and 0.06), as well as Kuroski’s [15] result for U0.8Pu0.2O2. The
same trend exist among their results and the MD simulated lattice parameters135
of U0.75Pu0.25O2 in the temperature range from 300 to 2300K. The calculated
lattice constants of U0.75Pu0.25O2−x(x = 0.0, 0.02, 0.06) agree well with both
Arima and Kuroski data of U0.8Pu0.2O2−x(x = 0.0, 0.02, 0.06), which indicates
that the change (5%) of Pu concentration rarely affect lattice parameters of
8
MOX. Fig. 3 shows an increase in lattice constant of U0.75Pu0.25O2−x with140
increasing both oxygen vacancy x and temperature. Unfortunately, no avail-
able experimental or theoretical data to compare with our results in the high-
temperature and high oxygen deficiency conditions. The phenomenon of lattice
expansion is mainly cased by the presence of vacancies, the larger size of the
+3 ions, and the reduced strength of Coulombic interactions arising from the145
replacement of +4 ions by +3 ions, which had been reported by Watanabe [17]
in their previous work.
4.2. Linear thermal expansion coefficient
The linear thermal expansion coefficient (αlin) of (U0.75Pu0.25) O2−x can
be evaluated from the variation of the lattice parameters with temperature as150
follow:
αlin = 1L(T0)
(∂(L)∂T )
P, (2)
where L could be either unit cell length or the MD cell length. In the case
of (U0.75Pu0.25)O2−x, there is little experimental data for the linear thermal
expansion coefficient.
The averaged thermal expansion coefficients (temperature range 300-1270K)155
of present MD calculation when x=0.02 and 0.06 are plotted in Fig. 4, and
compared with previous determinations of (U1−yPuy)O2−x(y ∼ 19.1− 25%) by
Leblanc et al. [27], Lorenzelli et al. [28], Roth et al. [29], Gibby et al.[30] and
Arima et al. [1] The results are in good agreement with the literature data, and
consistent with Arima’s findings surprisingly.160
The variation of linear thermal expansion coefficient with temperature is
shown in Fig. 5, along with the results of (U1−yPuy)O2 (y = 0.2, 0.25) from
Martin [31], Skavdahl et al [32]. and Gibby [30]. The tendency is consistent
with previous research results, which the linear thermal expansion coefficient
increases with increasing temperature. It is a known fact that the interatomic165
spacing between the atoms is a function of temperature, and the atoms will
9
Figure 4: Calculated results of thermal expansion coefficient for (U0.75Pu0.25)O2−x as a
function of O/M ratio.
10
Figure 5: Calculated results of linear thermal expansion coefficient for (U0.75Pu0.25)O2−x as
a function of temperature.
vibrate and move further apart resulting from the increase of temperature. The
linear thermal expansion coefficients of (U0.75Pu0.25)O2−x increase with tem-
perature. The impact of the concentration of oxygen vacancy is negligible when
the temperature falls below 1300K, but that became obvious with the increas-170
ing temperature, especially x = 0.25. These results indicate that the values of
oxygen vacancy have a larger effect on the linear thermal expansion coefficient
in high temperature range.
4.3. Compressibility and Bulk modulus
The isothermal compressibility can be expressed as follows:175
β = − 1V (P0)
(∂(V )∂P )T , (3)
where P and V stand for pressure and volume (lattice), respectively. At the all
temperature range from 300 to 3000K, the compressibility was evaluated by the
11
Figure 6: Compressibility of (U0.75Pu0.25)O2−x as a function of temperature.
change of lattice volume with varying pressure from 0.1MPa to 1.5GPa under the
NPT ensemble. The variation of isothermal compressibility of (U0.75Pu0.25)O2−x
with temperature, along with Yamada’s [9] MD result of UO2 are shown in Fig.180
6. Yamada’s result show rapid increase beyond 2200K, where have a Bredig
transition due to the instability in oxygen sublattice. However, unstable oxy-
gen sublattice does not guarantee a drastic rise [33], because cation sublattice
might well remain stable above 2000K. We notice that our isothermal compress-
ibility of (U0.75Pu0.25)O2−x slightly increases with increasing temperature. In185
addition, the results suggest that the compressibility increases with x values of
oxygen deficiency, but the rate of increase with temperature is almost same at
different values of x.
The bulk modulus is defined as the reciprocal of the compressibility. In
this work, we present comparisons between our MD simulated values of bulk190
modulus of (U0.75Pu0.25)O2−x and the Arima’s results of (U0.8Pu0.2)O2−x (x =
0.02, 0.06) which are shown in Fig. 7. Although in the case of slightly different
12
Figure 7: Calculated results of bulk modulus for (U0.75Pu0.25) O2−x as a function of O/M
ratio, together with literature data.
13
ratios of Pu content, our calculated results for x = 0.02 and 0.06 are in excellent
agreement with Arima’s theoretical results. The phenomenon demonstrates
that the effect of plutonium concentration appears to be relatively small to the195
bulk modulus. The bulk modulus decreases with increasing temperatures and x
values of oxygen deficiency. When x = 0.02, 0.06, the temperature dependence of
the bulk modulus can be treated in two temperature regions: a gradual decrease
at low temperatures (below 1000K) and a rapid decrease at high temperatures.
However, when oxygen deficiency x > 0.2 , the bulk modulus decreases linearly200
with increasing temperature.
4.4. Thermal conductivity
The thermal conductivity was calculated by the Green-Kubo approach [34]
in equilibrium Molecular Dynamics (EMD) system. The Green-Kubo formulas
which relate the ensemble average of the auto-correlation function of the heat205
flux is usually given by:
κ =V
3KBT 2
∫ ∞
0
J(t)J(0)dt, (4)
where KB is the Boltzmanns constant, V is the simulated cell volume ,T is
the absolute temperature, and J(t) is the heat flux for the simulated cell [35].
The heat flux can be calculated from the fluctuations of per-atom potential
and kinetic energies, and per-atom stress tensor in a steady-state equilibrated
simulation. It is usually given by:
J =1V
∑i
eiVi +12
∑i<j
(fij (Vi + Vj))Xij
, (5)
where Vi is the velocity of atom i , fij andXij are the atomic force and distance
between i andj , respectively. ei is the instantaneous excess energy of atom i
which is given by:
ei =
12miv
2i +
12
∑i=j
u (rij)
− eav, (6)
14
Figure 8: Thermal conductivity for (U0.75Pu0.25)O2−x as a function of temperature.
where eav is the average energy of the system, mi is the mass of atom i, u is
the atomic potential between atom i and j , respectively.
In this work, we evaluated the thermal conductivity of (U0.75Pu0.25) O2−x210
(x = 0.0, 0.02, 0.06, 0.1, 0.15, 0.2, 0.25) by MD calculation in the temperature
range between 300K and 3000K. The thermal conductivity as a function of tem-
Table 2: Plutonium concentration dependence of thermal conductivitya of U1−yPuyO2.
Temperature UO2 U1−yPuyO2
(K) Busker Yamada y = 0.15 y = 0.2 y = 0.25 y = 0.3500 7.52 9.25 9.340 9.282 9.671 9.3781000 3.33 3.42 4.239 3.561 3.457 3.4891500 2.28 2.45 1.982 1.780 2.147 1.9362000 1.31 1.40 1.298 1.361 1.544 1.501
aThermal conductivities are in Wm−1K−1.
15
perature is shown in Fig. 8, together with data listed in literatures [1, 4, 5, 36].
Although only the lattice contribution to the thermal conductivity can be eval-
uated in the present case, the results of calculated thermal conductivity are con-215
sistent with the experiment data and theoretical values in the low temperature
and low oxygen deficiency (x = 0.02, 0.06) ranges. From the reports of Arima
et al. [10], we have known that the contribution of lattice defects (i.e. oxygen
vacancies) to thermal conductivity is large at low temperatures, whereas the
Umklapp process (phonon∼phonon interactions) dominates lowering the ther-220
mal conductivity at high temperatures. It is obvious that our calculated thermal
conductivities clearly decrease with temperature increasing and show the same
tendency with the results of Arima et al. [1], Ionue [5] and Mihaila et al. [36].
Philipponeau’s [4] recommendation consequences seem to give somewhat lower
values in the temperature range 500−1700K, this phenomenon may result from225
chemical instability of MOX which was pointed out by Inoue [5]. Furthermore,
with increasing x values of oxygen deficiency, the thermal conductivity decreases
obviously, and the degree of the temperature dependence also decrease. In or-
der to investigate the influence of Pu concentration, we further calculated the
thermal conductivity of U1−yPuyO2 (y = 0.15, 0.2, 0.25, 0.3) and compared with230
Watanabe’s [16] values of UO2 using Busker and Yamada potentials, which are
listed in table. 2. The deviation of thermal conductivity made by the different y
is not obvious, which indicate that the influence of Pu concentration is so small
that it can be ignored compared with impact of oxygen defect. Therefore, the
oxygen vacancy plays a more important role than the difference of plutonium235
concentration in evaluating the thermal conductivity of MOX fuel.
5. Conclusions
In summary, the lattice parameter, linear thermal expansion coefficient, com-
pressibility, bulk modulus and thermal conductivity of (U0.75Pu0.25)O2−x (x =
0.0, 0.02, 0.06, 0.1, 0.15, 0.2, 0.25) have been investigated through MD simula-240
tions using the BMH potential with the PIM in the temperature range between
16
300 and 3000K. The temperature dependences of calculated lattice parameter,
linear thermal expansion coefficient and compressibility for U0.75Pu0.25O2−x
well agree with the experimental observations and theoretical data in the low
temperature and low oxygen deficiency ranges. The calculated values of bulk245
modulus at x = 0.02, 0.06 are in good agreement with Arima’s theoretical data,
and gradually tend to be linear relationship with temperature when oxygen
deficiency x > 0.2. We also find that the oxygen vacancies have a significant
effect on thermal properties of MOX, especially thermal conductivity. As oxy-
gen vacancies increase, the thermal conductivity decreases very clearly, and the250
temperature dependence weakens. When oxygen vacancies are existent, the in-
fluence of plutonium concentration for thermal conductivity is so small that
it can be ignored. In addition, we provide a more complete data of physical
properties of MOX by MD simulation.
6. Acknowledgments255
The author J.G.Du acknowledges the funding supporting from National Nat-
ural Science Foundation of China (NO.11204193).
References
[1] T. Arima ,S. Yamasaki, Y. Inagaki, K. Idemitsu, J. Alloys Compd. 415
(2006) 43.260
[2] C. Duriez, JP. Alessandri, T. Gervais, Y. Philipponnesu, J. Nucl. Mater.
277 (2000) 143.
[3] D.G. Martin, J. Nucl. Mater. 110 (1982) 73.
[4] Y. Philipponneau, J. Nucl. Mater. 188 (1992) 194.
[5] M. Inoue, J. Nucl. Mater. 282 (2000) 186.265
[6] Hua Y. Geng, Y. Chen, Y. Kaneta, M. Iwasawa, T. Ohnuma, M. Kinoshita,
Phys. Rev. B 77 (2008) 104120.
17
[7] M. Stan, P. Cristea, J. Nucl. Mater. 344 (2005) 213.
[8] R. Gibby, J. Nucl. Mater. 38(2) (1971) 163.
[9] K. Yamada, K. Kurosaki, M. Uno, S. Yamanaka, J. Alloys Compd. 307270
(2000) 10.
[10] T. Arima, S. Yamasaki, Y. Inagaki, K. Idemitsu, J. Alloys Compd. 400
(2005) 43.
[11] S. Nichenko, D. Staicu, J. Nucl. Mater. 433 (2013) 297.
[12] M.J. Wan, L. Zhang, J.G. Du, D.H. Huang, L.L. Wang, G. Jiang, Physica275
B 407 (2012) 4595.
[13] K. Govers, S. Lemehov, M. Hou, M. Verwerft, J. Nucl. Mater. 395 (2009)
131.
[14] L. Ma, A.K. Ray, Eur. Phys. J. B 81 (2011) 103.
[15] K. Kurosaki, K. Yamada, M. Uno, S. Yamanaka, K. yamamoto, T.280
Namekawa, J. Nucl. Mater. 294 (2001) 160.
[16] T. Watanabe, S. B. Sinnott, J. S. Tulenko, R. W. Grimes, P. K. Schelling,
S. R. Phillpot, J. Nucl. Mater. 375 (2008) 388.
[17] T. Watanabe, S. G. Srivilliputhur, P. K. Schelling, J. S. Tulenko, S.
B.Sinnott, S. R. Phillpot, J. Am. Ceram. Soc. 92[4] (2009) 850.285
[18] S.J. Plimpton, J. Comput. Phys. 117 (1995) 1.
[19] W.G. Hoover, Phys. Rev. A 34 (1986) 2499.
[20] S. Melchionna, G. Ciccotti, B.L. Holian, Mol. Phys. 78 (1993 )533.
[21] P. K. Schelling, S. R. Phillpot, P. Keblinski, Phys. Rev. B 65 (2002) 144306.
[22] H. Inaba, R. Sagawa, H. Hayashi, K. Kawamura, Solid State Ionics 122290
(1999) 95.
18
[23] H. Hayashi, R. Sagawa, H. Inaba, K. Kawamura, Solid State Ionics 131
(2000) 281.
[24] S. Nichenko, D. Staicu, J. Nucl. Mater. 439 (2013) 93.
[25] P.M. Morse, Phys. Rev. 34 (1929) 57.295
[26] M. Beauvy, J. Nucl. Mater. 188 (1992) 232.
[27] J.M. Leblance, H. Andriessen, EURATOM/USA Rep.EURAEC-434
(1962).
[28] R. Lorenzelli, M. El Sayed Ali, J. Nucl. Mater. 68 (1977) 100.
[29] J. Roth, M.E. Hubert, J.R. Cherry, C.S.Caldwell, Trans. Am. Nucl. Soc.300
10 (1967) 457.
[30] R.L. Gibby, Hanford Quarterly Technical Rep, July-Sep.1974, Ed. E.A.
Evans, HEDL-TME 74-3, Vol.1, p.A-8.
[31] D. Martin, J. Nucl. Mater. 152 (1987) 94.
[32] R.E. Skavdahl, E.L. Zebroski, General Electric Rep. Geap-5700. (1968) 57.305
[33] C.B. Basak, A.S. Kolokol, J. Am. Ceram. Soc. 95[4] (2012) 1435.
[34] M. Green, J. Chem. Phys. 22(3) (1954) 398.
[35] P. Sindzingre, M.J. Gillan, J. Phys. Cond. Matter 2 (1990) 7033.
[36] B.Mihaila, M.Stan, J.Crapps, D.Yun, J. Ncul. Mater. 433 (2013) 132.
19