Computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions
Problem of construction material composition changes induced by neutron fluxes of nuclear reactor VVER-1000 as a
 result of a nuclear reaction and associated activation processes was considered. The special methodic to simulate this
 processes using computer simulation methods was de...
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
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| Zitieren: | Computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions / Y.V. Rudychev, M.A. Khazhmuradov, S.I. Prokhorets, D.V. Fedorchenko // Вопросы атомной науки и техники. — 2009. — № 5. — С. 40-45. — Бібліогр.: 5 назв. — англ. |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1860262686825119744 |
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| author | Rudychev, Y.V. Khazhmuradov, M.A. Prokhorets, S.I. Fedorchenko, D.V. |
| author_facet | Rudychev, Y.V. Khazhmuradov, M.A. Prokhorets, S.I. Fedorchenko, D.V. |
| citation_txt | Computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions / Y.V. Rudychev, M.A. Khazhmuradov, S.I. Prokhorets, D.V. Fedorchenko // Вопросы атомной науки и техники. — 2009. — № 5. — С. 40-45. — Бібліогр.: 5 назв. — англ. |
| collection | DSpace DC |
| container_title | Вопросы атомной науки и техники |
| description | Problem of construction material composition changes induced by neutron fluxes of nuclear reactor VVER-1000 as a
result of a nuclear reaction and associated activation processes was considered. The special methodic to simulate this
processes using computer simulation methods was developed. Stainless steel H18N10T composition changes during
a long irradiation time was simulated.
Розглянуто проблема змiни складу конструкцiйних матерiалiв реактора ВВЭР-1000 у результатi
ядерних реакцiй i вiдповiдних активацiйних процесiв, якi проходять у матерiалi пiд впливом нейтронного опромiнення протягом тривалого перiоду експлуатацiї матерiалу в умовах нейтронного потоку
реактора ВВЭР-1000. Для моделювання подiбних завдань розроблена спецiальна методика, заснована
на сучасних методах комп’ютерного моделювання. Проведено моделювання змiни iзотопного складу
аустенiтної сталi Х18Н10Т пiд дiєю нейтронного опромiнення протягом тривалого часу.
Рассмотрена проблема изменения состава конструкционных материалов реактора ВВЭР-1000 в результате ядерных реакций и соответствующих активационных процессов, которые проходят в материале под воздействием нейтронного облучения в течение длительного периода эксплуатации материала,
в условиях нейтронного потока реактора ВВЭР-1000. Для моделирования подобных задач разработана
специальная методика, основанная на современных методах компьютерного моделирования. Проведено
моделирование изменения изотопного состава аустенитной стали Х18Н10Т под действием нейтронного
облучения в течение длительного времени.
|
| first_indexed | 2025-12-07T18:57:29Z |
| format | Article |
| fulltext |
COMPUTER SIMULATIONS OF THE STAINLESS STEEL
COMPOSITION CHANGES INDUCED BY NEUTRON BASED
NUCLEAR REACTIONS
Y.V. Rudychev, M.A. Khazhmuradov ∗, S.I. Prokhorets, D.V. Fedorchenko
National Science Center ”Kharkov Institute of Physics and Technology”, 61108, Kharkov, Ukraine
(Received June 3, 2009)
Problem of construction material composition changes induced by neutron fluxes of nuclear reactor VVER-1000 as a
result of a nuclear reaction and associated activation processes was considered. The special methodic to simulate this
processes using computer simulation methods was developed. Stainless steel H18N10T composition changes during
a long irradiation time was simulated.
PACS: 28.41.Qb, 24.10.Lx, 25.40.Fq, 23.40.–s, 29.25.Dz, 23.60.+e, 28.60.+s, 61.80.Hg
1. INTRODUCTION
The life time extension of operational nuclear
power plains is a critical problem of Ukrainian energy
industries. Solution of this problem is significant low
cost operation as compared with new nuclear power
plaint production. This is especially important be-
cause of limited building power of a new VVER-1000
power unit in Russian Federation. Physical state-
ment and support of life time extension of nuclear
power plains is elaborate and complex problem. This
required participation of many specialists from dif-
ferent fields of science. One of the possible ways of
solution this problem is an investigation of stainless
steel X18H10T as a constructional material of reactor
vessel and in-vessel component[1]. Within the bounds
of this one of the possible methods is making of im-
itational experiments. These experiments are irradi-
ations of given constructional materials by different
kind and energy ions in goal to simulate the same con-
ditions for radiation induced composition changes as
under irradiation by nuclear reactor. Unfortunately,
because of different nature of neutron and ion irra-
diation, the misfit between results of imitational ex-
periments and reactor irradiations is observed.
In a given work, using special simulation meth-
ods, the problem of the stainless steel composition
changes induced by neutron fluxes of nuclear reactor
VVER-1000 as a result of a nuclear reaction and as-
sociated activation processes is considered. It is nec-
essary to note that during imitational experiments
impossible to taking into account such processes be-
cause of no neutron fluxes exist in this case. As
in our case we have long time neutron irradiation.
Therefore the significant initial compositions changes
are possible by activation processes of transmuta-
tion in given material. Production of hydrogen and
helium by 56Fe(n, p)56Mn → p + e− → 1H and
56Fe(n, α)53Cr → α + 2e− → 4He reactions plays
significant role in initial composition changes.
Production of given gases combined with radia-
tion damages effects may lead to significant material
properties changes.
2. SIMULATION TECHNIQUES
General principles of solution of given tasks are
calculation of concentration of the given elements
depending on irradiation time. Isotope transmu-
tation and activation processes physically grounded
on nuclear reactions induced by external elemen-
tary particle source or secondary particles of de-
cayed isotopes. Examples of such reactions are
(γ, n), (γ, p), (p, n), (n, α) and other ones.
In present moment the most of well-known meth-
ods of simulations of activation and transmutation
processes based on solution of differential equations of
concentration changes. Main trouble in given meth-
ods consist of define of reactions cross-sections and
define of fluxes and energy spectrums of the given
particles with was induced by this reactions. Most
of modern’s objects of investigations are complicated
3D systems with complex heterogeneous structures
such as devices, constructive elements and other. De-
finition of fluxes and spectra of radiation transport
problems was initially attempted on the basis of the
Boltzmann transport equation. However, this proce-
dure comes up against considerable difficulties when
applied to limited geometries as written above, with
the result that numerical methods based on the trans-
port equation have only had certain success in sim-
ple geometries, mainly for unlimited and semi-infinite
media. Hence for this case the special complex me-
thodic was developed. Conceptual scheme of this me-
thodic is represented on Fig. 1.
∗Corresponding author. E-mail address: khazhm@kipt.kharkov.ua
40 PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY, 2009, N5.
Series: Nuclear Physics Investigations (52), p.40-45.
Fig.1. Conceptual scheme of developed simulation
methodic
In this methodic all radiation transport character-
istics were defined directly by Monte Carlo method.
After that obtained results were used as a data for
applying in iteration system of solution of differential
equation set.
As tools for realization of given scheme the sev-
eral special codes were used. As Monte Carlo simu-
lation tools the widely-used particle transport codes
GEANT4 and MCNPX were chosen[2],[3].
These codes provide adequate description of all
necessary physical processes and have possibility of
implementation of 3D geometry of investigation ob-
ject with very complicate structure. All results ob-
tained from MC codes prepared by special procedure
for using them as initial data for solution of corre-
sponding time-evolving differential equations.
For this task the special code FISPACT was
chosen[4]. FISPACT uses external libraries of reac-
tion cross sections and decay data for all relevant nu-
clides to calculate an inventory of nuclides produced
as a result of the irradiation of a starting material
with a flux of neutrons. The actual output quantities
include the amount (number of atoms and grams),
the activity (Bq),α,β and γ-energies (kW),γ - dose-
rate (Sv h−1), the potential ingestion and inhala-
tion doses (Sv), the legal transport limit (A2 value),
the clearance index and the half-life for each nuclide.
Amounts and heat outputs are also given for the el-
ements and the γ-ray spectrum for the material is
listed as well as various summed quantities, such as
total activity and total dose-rate. At the end of each
time interval the dominant nuclides (in terms of ac-
tivity, heat, dose-rate, potential biological hazards
and clearance index) and the pathway data for the
production of these nuclides can be shown. The un-
certainties in eight total radiological quantities can
be calculated and output. As options, data files can
be produced for subsequent use by other programs
to plot graphs of the total responses as functions of
elapsed time and selected blocks of output may be
written to external data files.
The core task of FISPACT is the solution of a set
of differential equations that describe the amounts of
atoms of various nuclides present following the irra-
diation of a given material in a neutron field. The
set of differential equations is given in equation (1).
dNi
dt
= −Ni(λi + σiφ) +
∑
i6=j
Nj(λij + σijφ) + Si ,
Si =
∑
k
Nkσf
kφYik , (1)
where Ni is the amount of nuclide i at time t; λi is
the decay constant of nuclide i [s−1]; λij is the decay
constant of nuclide j producing i [s−1]; σi is the total
cross section for reactions on i [cm−2]; φ is the neu-
tron flux [n cm2 s−1]; σij is the reaction cross section
for reactions on j producing i [cm2]; σf
k is the fission
cross section for reactions on actinide k [cm2];Yik is
the yield of nuclide i from the fission of nuclide k. Si
is the source of nuclide i from fission. The final term
is only required if actinides are included in the initial
material.
It is necessary to use an efficient method of so-
lution of the set of equations in (1). Since the to-
tal number of nuclides considered is over 1900. The
method used in FISPACT is that of Sidell[5]. This
method is an extension of the Euler (first order Taylor
series) which uses an exponential function of the step
length. Equation (2) shows the standard Euler solu-
tion and (3) the Sidell solution for the step time h.
Ni(h + t) = Ni(t) + h
dNi
dt
∣∣∣∣
t
, (2)
Ni(h + t) = Ni(t) + h
(eΛih − 1)
Λi
dNi
dt
∣∣∣∣
t
. (3)
The error in using (3) is lower than (2), but for
stability of the solution it is still necessary that the
time step be related to the reciprocal of the largest
eigenvalue. For this reason a restriction is placed on
the largest eigenvalue considered (some nuclides are
considered in equilibrium). The number of steps in
the computational solution of the Sidell method is
greater than the Euler method, but not sufficiently
to outweigh the advantages. The procedure is to split
the irradiation time into two steps, perform the cal-
culation, test the convergence of all the nuclides and,
if the test fails then repeat with double the number
of time steps. This procedure is continued until suffi-
cient accuracy is achieved. The results at each stage
are corrected using the results from the previous stage
(’extrapolation’) to improve the convergence of the
solution.
41
Experience with this solution method in
FISPACT shows that it is rapid to converge and able
to give sufficient accuracy. The code implements a
maximum number of iteration stages is 10, but if
convergence has not been achieved by then it is usu-
ally only for a very few ’unimportant’ nuclides. The
output flags these nuclides, thus enabling the worth
of the particular ’non-converged’ run to be judged.
It was mentioned above that there is a limit on the
largest eigenvalue considered in the solution of the
equations. This means that physically only nuclides
with sufficiently long half-lives are calculated by the
above method. The remainder is assumed to be in
equilibrium, and thus their values can be written
down immediately as shown in equation (4)
Nequil
i = (λi + σiφ)−1
∑
j
Nj(λij + σijφ) . (4)
The half-life at which nuclides are considered to be
in equilibrium is under the control of the user. This
is done by choosing the time interval (code word
TIME) and the parameters following the LEVEL
code word. FISPACT requires connection to several
data libraries before it can be used to calculate in-
ventories. While any libraries in the correct format
could be used, the development of FISPACT over
the last few years has run in parallel with the de-
velopment of the European Activation File and this
EAF library is the recommended source of cross sec-
tion data. Therefore in our scheme EAF library was
used.
3.THE SIMULATION OF ACTIVATION OF
STAINLESS STEEL H18N10T
For first approximation of a given task we decided
to simplify scheme of simulation because of complete
cycle of computation applying to VVER-1000 reac-
tors by Monte Carlo methods spend a lot computer
time. In other hand fluxes and energies have no
significant differences compare to averaged values of
neutron spectra. Therefore the averaged spectrum
for VVER-1000 reactors type was used. The spe-
cial 69 group’s representation of this spectrum called
WIMS was used. This method of presentation makes
it clear in which energy ranges particular structures
have most groups and will therefore give a good rep-
resentation of the cross sections. The average burn
up was 1 MW/kg and an average neutron flux was
2.6693×1014 n/cm2 per second. This spectrum is
shown on Fig. 2.
Fig.2. Neutron spectrum during stainless steel
irradiation
Composition of H18H10T steel was chosen without
taking into account a doping material.Initial compo-
sition of given steel normalized by 1 kg is shown in
Table 1.
Table 1. Composition of initial stage of H18N10T stainless steel
Isotope Number of atoms Mass, gram
C12 4.96E+22 9.88E-01
C13 5.57E+20 1.20E-02
Ti46 1.04E+22 7.92E-01
Ti47 9.36E+21 7.30E-01
Ti48 9.27E+22 7.38E+00
Ti49 6.81E+21 5.53E-01
Ti50 6.52E+21 5.41E-01
Cr50 9.06E+22 7.51E+00
Cr52 1.75E+24 1.51E+02
Cr53 1.98E+23 1.74E+01
Cr54 4.93E+22 4.42E+00
Fe54 4.47E+23 4.00E+01
Fe56 7.02E+24 6.52E+02
Fe57 1.62E+23 1.53E+01
Fe58 2.16E+22 2.07E+00
Ni58 6.98E+23 6.72E+01
Ni60 2.69E+23 2.68E+01
Ni61 1.17E+22 1.18E+00
Ni62 3.73E+22 3.83E+00
Ni64 9.50E+21 1.01E+00
42
Simulation of activation processes was done ac-
cording written above scheme for 1, 5, 10, 20 and 30
years of irradiation time. Results of this simulation
for produced isotopes amount more then 108 atoms
in H18N10T stainless steel after 30 years irradiation
time is shown in Table 2.
Table 2. Isotopes composition in H18N10T stainless steel after 30 years irradiation time
Isotope Number of Mass, gm Activity, Half-life, Isotope Number of Mass,gm Activity, Half-life,
atoms Bq s atoms Bq s
H1 1.26E+22 2.10E-02 - Stable Cr50 6.83E+22 5.67E+00 - Stable
H2 3.60E+19 1.20E-04 - Stable Cr51 6.92E+19 5.86E-03 2.01E+13 2.39E+06
H3 6.59E+15 3.30E-08 1.17E+07 3.89E+08 Cr52 1.72E+24 1.49E+02 - Stable
He3 1.21E+14 6.05E-10 - Stable Cr53 1.66E+23 1.46E+01 - Stable
He4 4.92E+21 3.27E-02 - Stable Cr54 1.09E+23 9.77E+00 - Stable
Li6 8.16E+14 8.15E-09 - Stable Cr55 2.35E+14 2.14E-08 7.65E+11 2.12E+02
Li7 7.76E+11 9.04E-12 - Stable Mn53 2.26E+16 1.99E-06 1.35E+02 1.16E+14
Be9 4.80E+18 7.19E-05 - Stable Mn54 1.12E+20 9.99E-03 2.86E+12 2.70E+07
Be10 7.93E+16 1.32E-06 1.09E+03 5.05E+13 Mn55 1.42E+22 1.30E+00 - Stable
B10 1.54E+10 2.56E-13 - Stable Mn56 6.35E+16 5.90E-06 4.74E+12 9.28E+03
B11 8.25E+11 1.51E-11 - Stable Mn57 4.79E+12 4.53E-10 3.44E+10 9.66E+01
C12 4.96E+22 9.88E-01 - Stable Mn58 1.34E+09 1.29E-13 1.43E+07 6.52E+01
C13 5.60E+20 1.21E-02 - Stable Fe54 4.26E+23 3.82E+01 - Stable
C14 2.53E+16 5.87E-07 9.68E+04 1.81E+11 Fe55 2.28E+21 2.08E-01 1.83E+13 8.63E+07
N14 4.51E+13 1.05E-09 - Stable Fe56 6.70E+24 6.23E+02 - Stable
N15 5.95E+10 1.48E-12 - Stable Fe57 4.66E+23 4.41E+01 - Stable
Ar38 9.37E+09 5.91E-13 - Stable Fe58 4.04E+22 3.88E+00 - Stable
Ar39 3.72E+10 2.41E-12 3.04E+00 8.49E+09 Fe59 6.63E+18 6.49E-04 1.20E+12 3.85E+06
Ar40 1.89E+14 1.26E-08 - Stable Fe60 1.11E+18 1.10E-04 1.62E+04 4.73E+13
Ar42 1.81E+10 1.26E-12 1.20E+01 1.04E+09 Fe61 1.02E+10 1.03E-12 1.97E+07 3.59E+02
K39 9.84E+08 6.37E-14 - Stable Co57 5.76E+15 5.45E-07 1.70E+08 2.35E+07
K41 1.48E+12 1.01E-10 - Stable Co58 2.99E+19 2.88E-03 3.38E+12 6.12E+06
K42 9.15E+08 6.38E-14 1.43E+04 4.45E+04 Co58m 1.24E+17 1.19E-05 2.66E+12 3.22E+04
K43 1.66E+10 1.19E-12 1.44E+05 7.99E+04 Co59 1.45E+21 1.42E-01 - Stable
Ca42 1.46E+15 1.02E-07 - Stable Co60 3.07E+20 3.05E-02 1.28E+12 1.66E+08
Ca43 4.54E+17 3.24E-05 - Stable Co60m 8.71E+14 8.67E-08 9.61E+11 6.28E+02
Ca44 9.46E+17 6.91E-05 - Stable Co61 2.38E+14 2.41E-08 2.77E+10 5.94E+03
Ca45 1.34E+16 1.00E-06 6.62E+08 1.41E+07 Co62 4.29E+09 4.41E-13 3.30E+07 9.00E+01
Ca46 6.35E+16 4.85E-06 - Stable Co62m 2.00E+10 2.06E-12 1.66E+07 8.35E+02
Ca47 2.31E+12 1.80E-10 4.08E+06 3.92E+05 Ni58 6.38E+23 6.14E+01 - Stable
Ca48 6.03E+10 4.80E-12 - Stable Ni59 1.97E+22 1.93E+00 5.71E+09 2.40E+12
Sc45 5.17E+17 3.86E-05 - Stable Ni60 2.85E+23 2.83E+01 - Stable
Sc46 1.00E+17 7.66E-06 9.60E+09 7.24E+06 Ni61 2.50E+22 2.53E+00 - Stable
Sc46m 5.52E+10 4.21E-12 2.05E+09 1.87E+01 Ni62 2.99E+22 3.07E+00 - Stable
Sc47 6.56E+15 5.11E-07 1.57E+10 2.89E+05 Ni63 5.93E+21 6.20E-01 1.32E+12 3.12E+09
Sc48 3.92E+14 3.12E-08 1.73E+09 1.57E+05 Ni64 1.09E+22 1.16E+00 - Stable
Sc49 2.11E+12 1.72E-10 4.27E+08 3.43E+03 Ni65 4.10E+15 4.43E-07 3.14E+11 9.07E+03
Ti46 1.03E+22 7.83E-01 - Stable Cu63 6.99E+20 7.30E-02 - Stable
Ti47 9.15E+21 7.13E-01 - Stable Cu64 5.06E+15 5.37E-07 7.67E+10 4.57E+04
Ti48 8.12E+22 6.46E+00 - Stable Cu65 2.65E+20 2.86E-02 - Stable
Ti49 1.82E+22 1.48E+00 - Stable Cu67 1.38E+09 1.53E-13 4.28E+03 2.23E+05
Ti50 7.02E+21 5.82E-01 - Stable Zn64 1.02E+19 1.08E-03 - Stable
Ti51 1.24E+13 1.05E-09 2.47E+10 3.48E+02 Zn65 6.79E+15 7.32E-07 2.23E+08 2.11E+07
V50 2.27E+20 1.88E-02 3.34E-05 4.70E+24 Zn66 6.27E+18 6.86E-04 - Stable
V51 2.10E+22 1.78E+00 - Stable Zn67 4.10E+16 4.55E-06 - Stable
V52 6.78E+14 5.85E-08 2.09E+12 2.25E+02 Zn68 3.06E+15 3.45E-07 - Stable
V53 7.97E+11 7.01E-11 5.68E+09 9.72E+01 Zn70 2.41E+09 2.80E-13 - Stable
V54 1.09E+09 9.77E-14 1.52E+07 4.98E+01 Ga69 2.34E+13 2.68E-09 - Stable
Analysis of obtained results indicated that main
isotopes which were produced by neutron irradia-
tion are hydrogen, deuterium, helium, vanadium,
calcium, manganese, cobalt. After a long time of
irradiation additionally cooper and zinc were pro-
duced. The hydrogen production depending on
irradiation time was shown in Fig. 3. Produc-
tion of other major isotopes was shown in Fig. 4.
43
Fig.3. Hydrogen production depending on
irradiation time
Fig.4. Some major isotopes production depending
on irradiation time
Obtained results indicated that production of hy-
drogen is a result of (n, p) → p + e− →1 H reaction.
Reaction of such type lead to other isotopes produc-
tion for example production of vanadium, manganese,
cobalt as a result of 56Fe(n,p)56Mn, 52Cr(n,p)52V,
58Ni(n,p)58Co reactions. It is necessary to note that
production of other isotopes causes to other reactions
for example 58Ni(n,γ)59Ni(β +)59Co. Helium produc-
tion is exist because of (n, α) → α+2e− →4 He reac-
tion. Such kinds of reaction for iron lead to chromium
production for chromium lead to titanium production
and for titanium lead to calcium production also be-
cause of such reaction for nickel production of iron is
occur.
In a long irradiation time also production of
other isotopes is possible, for example a cooper pro-
duction from 62Ni(n,γ)63Ni(β −)63Cu(n,γ)64Cu reac-
tions. Velocity analysis of isotopes accumulation will
be realized in future investigation. But it is necessary
to note that velocity of isotopes accumulation mainly
depending on reaction cross-section and numbers of
active pathways during isotope production. Moreover
the main factor of accumulation velocity is a diffusion
and adhesive processes which were not taking into ac-
count in this investigation.
Developed simulation methodic create possibility
to make analysis of modification of isotopic compo-
sition of stainless steel H18N10T under long time
irradiation such steel by neutrons with energy dis-
tribution corresponding to spectrum of VVER-1000
reactor. In our simulation we taking into account
all active pathways of isotopic production. Also the
modern reaction and decay data bases during simu-
lation processes were used. Using our simulation me-
thodic modification of composition steel by nuclear
reaction of transmutation was obtained. Obtained re-
sults proved that main process under steel activation
is productions of such isotopes as hydrogen, helium,
vanadium, manganese and cobalt.
In future investigation will be necessary to make
analysis of chemical composition changes of a given
material after irradiation in more detail. Hence, it is
possible to modify methodic for specific purposes and
choose from obtained isotopes most important ones
with relation to a solid state physics. Also we will
take into account diffusion and other processes which
will have an influence on gases migration in material.
Applying of the given simulation methodic is more
reasonable as a part of radiation physics investiga-
tion. It is necessary for adequate model development
with taking into account major physical processes
which will be active in material under irradiation.
4. CONCLUSIONS
Developed simulation methodic create possibility
to provide simulation of activation processes in condi-
tion of high intensity neutron fluxes of stainless steel
H18N10T during long irradiation period.
This simulation methodic by applying of the most
modern data bases such as EAF Cross Section and
EAF Decay allow to simulate modification of iso-
topic composition of a given material with taking into
account all possibly reactions of isotopic production
which will be active under neutron irradiation.
Analysis of obtained results indicates that major
elements which will be accumulate during irradiation
time in material are helium and hydrogen.
In future plans we are going to make co-operative
investigation in a nuclear physics field and in a radi-
ation damages physic field for the purpose of devel-
opment of complex simulation model of construction
materials behavior under neutron irradiation. Ac-
cording this activity it is necessary to have collabo-
ration with specialists in a field of radiation damages
and diffusion processes.
References
1. G.A. Filippov, P.A. Antikajn. Primenenie
suschestvuyuschih konstrukcionnyh materialov
dlya izgotovleniya vnutrikorpusnyh ustrojstv i
teplovydelyayuschih sborok legkovodnyh reak-
torov // Teplo‘energetika. 2005, v.8, p.2-8 (in
Russian).
44
2. GEANT4 Physics Reference Manual. GEANT4
Working Group. CERN, June 21, 2004.
3. J. Breismeister. Ed. MCNP - A General Monte
Carlo N-Particle Transport Code. LA-13709-M.
Los Alamos National Laboratory: Los Alamos,
NM, 2000.
4. R.A. Forrest. FISPACT-2003: User manual.
UKAEA FUS 485. 2002.
5. J. Sidell. EXTRA - A digital computer program
for the solution of stiff sets of ordinary value, first
order differential equations. Atomic Energy Es-
tablishment of Winfrith (AEEW-R).-799, 1972.
КОМПЬЮТЕРНОЕ МОДЕЛИРОВАНИЕ ИЗМЕНЕНИЯ СОСТАВА
НЕРЖАВЕЮЩЕЙ СТАЛИ, ИНДУЦИРОВАННОЕ НЕЙТРОННЫМИ ЯДЕРНЫМИ
РЕАКЦИЯМИ
Е.В. Рудычев, С.И. Прохорец, М.А. Хажмурадов, Д.В. Федорченко
Рассмотрена проблема изменения состава конструкционных материалов реактора ВВЭР-1000 в ре-
зультате ядерных реакций и соответствующих активационных процессов, которые проходят в матери-
але под воздействием нейтронного облучения в течение длительного периода эксплуатации материала,
в условиях нейтронного потока реактора ВВЭР-1000. Для моделирования подобных задач разработана
специальная методика, основанная на современных методах компьютерного моделирования. Проведено
моделирование изменения изотопного состава аустенитной стали Х18Н10Т под действием нейтронного
облучения в течение длительного времени.
КОМП’ЮТЕРНЕ МОДЕЛЮВАННЯ ЗМIН СКЛАДУ НЕРЖАВIЮЧОЇ СТАЛI,
IНДУКОВАНИХ НЕЙТРОННИМИ ЯДЕРНИМИ РЕАКЦIЯМИ
Є.В. Рудичев, С.I. Прохорець, М.А. Хажмурадов, Д.В. Федорченко
Розглянуто проблема змiни складу конструкцiйних матерiалiв реактора ВВЭР-1000 у результатi
ядерних реакцiй i вiдповiдних активацiйних процесiв, якi проходять у матерiалi пiд впливом нейтрон-
ного опромiнення протягом тривалого перiоду експлуатацiї матерiалу в умовах нейтронного потоку
реактора ВВЭР-1000. Для моделювання подiбних завдань розроблена спецiальна методика, заснована
на сучасних методах комп’ютерного моделювання. Проведено моделювання змiни iзотопного складу
аустенiтної сталi Х18Н10Т пiд дiєю нейтронного опромiнення протягом тривалого часу.
45
|
| id | nasplib_isofts_kiev_ua-123456789-96423 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-07T18:57:29Z |
| publishDate | 2009 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Rudychev, Y.V. Khazhmuradov, M.A. Prokhorets, S.I. Fedorchenko, D.V. 2016-03-16T19:37:16Z 2016-03-16T19:37:16Z 2009 Computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions / Y.V. Rudychev, M.A. Khazhmuradov, S.I. Prokhorets, D.V. Fedorchenko // Вопросы атомной науки и техники. — 2009. — № 5. — С. 40-45. — Бібліогр.: 5 назв. — англ. 1562-6016 PACS: 28.41.Qb, 24.10.Lx, 25.40.Fq, 23.40.–s, 29.25.Dz, 23.60.+e, 28.60.+s, 61.80.Hg https://nasplib.isofts.kiev.ua/handle/123456789/96423 Problem of construction material composition changes induced by neutron fluxes of nuclear reactor VVER-1000 as a
 result of a nuclear reaction and associated activation processes was considered. The special methodic to simulate this
 processes using computer simulation methods was developed. Stainless steel H18N10T composition changes during
 a long irradiation time was simulated. Розглянуто проблема змiни складу конструкцiйних матерiалiв реактора ВВЭР-1000 у результатi
 ядерних реакцiй i вiдповiдних активацiйних процесiв, якi проходять у матерiалi пiд впливом нейтронного опромiнення протягом тривалого перiоду експлуатацiї матерiалу в умовах нейтронного потоку
 реактора ВВЭР-1000. Для моделювання подiбних завдань розроблена спецiальна методика, заснована
 на сучасних методах комп’ютерного моделювання. Проведено моделювання змiни iзотопного складу
 аустенiтної сталi Х18Н10Т пiд дiєю нейтронного опромiнення протягом тривалого часу. Рассмотрена проблема изменения состава конструкционных материалов реактора ВВЭР-1000 в результате ядерных реакций и соответствующих активационных процессов, которые проходят в материале под воздействием нейтронного облучения в течение длительного периода эксплуатации материала,
 в условиях нейтронного потока реактора ВВЭР-1000. Для моделирования подобных задач разработана
 специальная методика, основанная на современных методах компьютерного моделирования. Проведено
 моделирование изменения изотопного состава аустенитной стали Х18Н10Т под действием нейтронного
 облучения в течение длительного времени. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Ядернo-физические методы и обработка данных Computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions Комп’ютерне моделювання змiн складу нержавiючої сталi, iндукованих нейтронними ядерними реакцiями Компьютерное моделирование изменения состава нержавеющей стали, индуцированное нейтронными ядерными реакциями Article published earlier |
| spellingShingle | Computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions Rudychev, Y.V. Khazhmuradov, M.A. Prokhorets, S.I. Fedorchenko, D.V. Ядернo-физические методы и обработка данных |
| title | Computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions |
| title_alt | Комп’ютерне моделювання змiн складу нержавiючої сталi, iндукованих нейтронними ядерними реакцiями Компьютерное моделирование изменения состава нержавеющей стали, индуцированное нейтронными ядерными реакциями |
| title_full | Computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions |
| title_fullStr | Computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions |
| title_full_unstemmed | Computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions |
| title_short | Computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions |
| title_sort | computer simulations of the stainless steel composition changes induced by neutron based nuclear reactions |
| topic | Ядернo-физические методы и обработка данных |
| topic_facet | Ядернo-физические методы и обработка данных |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/96423 |
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