A study of accelerator driven sub critical system - material using the CASCADE code
In the existing situation of experimental data required for design and modeling of ADS and
 similar other applications, development and benchmarking of the simulation codes for providing
 reliable data has become essential. Amongst the intra nuclear cascade codes, CASCADE code&#x...
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| Veröffentlicht in: | Вопросы атомной науки и техники |
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2009
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| Zitieren: | A study of accelerator driven sub critical system - material using the CASCADE code / V. Kumar, H. Kumawat, Chitra Bhatia // Вопросы атомной науки и техники. — 2009. — № 4. — С. 80-88. — Бібліогр.: 26 назв. — англ. |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1860250676459732992 |
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| author | Kumar, V. Kumawat, H. Chitra Bhatia |
| author_facet | Kumar, V. Kumawat, H. Chitra Bhatia |
| citation_txt | A study of accelerator driven sub critical system - material using the CASCADE code / V. Kumar, H. Kumawat, Chitra Bhatia // Вопросы атомной науки и техники. — 2009. — № 4. — С. 80-88. — Бібліогр.: 26 назв. — англ. |
| collection | DSpace DC |
| container_title | Вопросы атомной науки и техники |
| description | In the existing situation of experimental data required for design and modeling of ADS and
similar other applications, development and benchmarking of the simulation codes for providing
reliable data has become essential. Amongst the intra nuclear cascade codes, CASCADE code
which has been validated for the neutron production in proton collision with the high Z materials
in the past, has been used to study nuclear behavior of some of the prominent ADS materials
like, Th, U, Pb, Bi, W, Fe, Cr and Al in respect of reaction and production cross sections of
isotopes and neutrons in a wide range of energy, 11 MeV to several GeV. Emphasis has been
laid on the data of cross sections of (n, xn) reactions. It is found that their role is definite and
effective in deciding fuel combinations. The code provides neutron cross section data which
shows agreement with the existing experimental data and stresses need of further validation
using precision data from the accelerators.
За існуючого стану справ з експериментальними даними, які необхідні для
проектування та моделювання АDS (accelerator driven systems) і для інших аналогічних
застосувань, важливими стають розробка та еталонне тестування програм моделювання
для забезпечення отримання надійних даних. Із програм, що існують для
внутрішньоядерних каскадів, програма CASCADE, достовірність якої перевірялась для
народження нейтронів при зіткненні протонів з матеріалами, що мали в минулому
високий атомний номер Z, використовувалась для вивчення ядерної поведінки деяких
відомих матеріалів ADS (Th, U, Pb, Bi, W, Fe, Cr, Al) у відношенні перетинів реакцій та
перетинів народження ізотопів і нейтронів у широкому інтервалі енергій від 11 МеВ до
кількох гігаелектронвольт. Особлива увага приділялась даним щодо перeтинів реакцій (n,
xn). Встановлено, що вони грають визначну роль при виборі сполучень палива. Програма
забезпечує дані щодо нейтронних перетинів, які узгоджуються з існуючими
експериментальними даними, при цьому підкреслюється необхідність подальшої
перевірки з використанням точних даних від прискорювача.
При существующем положении дел с экспериментальными данными, требующимися
для проектировки и моделирования ADS (accelerator driven systems) и для других
аналогичных применений, становятся важными разработка и эталонное тестирование
программ моделирования для обеспечения получения надежных данных. Из программ,
существующих для внутриядерных каскадов, программа CASCADE, достоверность
которой проверялась для рождения нейтронов при столкновениях протонов с
материалами, имевшими в прошлом высокий атомный номер Z, использовалась для
изучения ядерного поведения некоторых известных материалов ADS (Th, U, Pb, Bi, W, Fe,
Cr и Al) в отношении сечений реакций и сечений рождения изотопов и нейтронов в
широком интервале энергий от 11 МэВ до нескольких гигаэлектронвольт. Особое
внимание уделялось данным о сечениях реакций (n, xn). Найдено, что они играют
определяющую роль при выборе сочетаний топлива. Программа дает данные о
нейтронных сечениях, которые находятся в согласии с существующими
экспериментальными данными, при этом подчеркивается необходимость дальнейшей
проверки с использованием точных данных от ускорителей.
|
| first_indexed | 2025-12-07T18:42:48Z |
| format | Article |
| fulltext |
A STUDY OF ACCELERATOR DRIVEN SUB CRITICAL SYSTEM -
MATERIAL USING THE CASCADE CODE
V. Kumar1, H. Kumawat2, and Chitra Bhatia1
1H.E.N.P.L. (ADS Program), Department of Physics, University of Rajasthan,
Jaipur, India;
2Nuclear Physics Division, B.A.R.C. Mumbai, India
E-mail: vkv1951@gmail.com; vkumarv1@sancharnet.in
In the existing situation of experimental data required for design and modeling of ADS and
similar other applications, development and benchmarking of the simulation codes for providing
reliable data has become essential. Amongst the intra nuclear cascade codes, CASCADE code
which has been validated for the neutron production in proton collision with the high Z materials
in the past, has been used to study nuclear behavior of some of the prominent ADS materials
like, Th, U, Pb, Bi, W, Fe, Cr and Al in respect of reaction and production cross sections of
isotopes and neutrons in a wide range of energy, 11 MeV to several GeV. Emphasis has been
laid on the data of cross sections of (n, xn) reactions. It is found that their role is definite and
effective in deciding fuel combinations. The code provides neutron cross section data which
shows agreement with the existing experimental data and stresses need of further validation
using precision data from the accelerators.
1. INTRODUCTION
With the availability of spallation neutrons
the field of nuclear science has once again
seen a spurt because of the possibility that
measurement of neutron cross sections at
higher than 20 MeV energy may be done with
high accuracy. Such data is highly demanded
in design and modeling of Accelerator Driven
Sub critical Systems (ADS), beam therapy,
shielding etc. and to fulfill the need of data to
verify nuclear models to advance the work of
simulation codes. Secondly, spallation source
being capable in copious yield of neutrons is
required in studies related to cold and ultra
cold neutrons. As mentioned, during the last
two decades enormous effort has been put in
developing various simulation codes which
generally encompass a big part of already
developed fundamental nuclear and particle
models and they are expected to be highly
useful in providing nuclear data for design and
modeling of nuclear devices such as ADS with
comparatively lesser efforts and time required
in conducting experiments. In this paper we
focus attention on one simulation code,
CASCADE code. For general features of many
such simulation codes of transport of nuclear
radiation through heterogeneous matter one is
advised to see reference [1].
The CASCADE code is based on the intra
nuclear cascade model of particle+nucleus
collision developed at JINR, Dubna by
Barashenkov and Toneev [2] and their
compilation of nuclear reaction data. In fact,
the compilation has worked like a school of
thought to a series of developments for
example Gudima, Mashnik and Toneev [3]
developed a version of the model in the form
of MARIAG code which later on modified to
Cascade Excitation Model (CEM-95) by
Mashnik [4] to give neutron multiplicity,
single and double differential spectra up to He4
and pions and fission yield not only in case of
proton interactions but even projectiles like
neutron and pions. Barashenkov, Shubin,
Konobeyev and Lunev in the year 1985 [5]
made an integrated effort for the extension of
the code up to TeV energy of particle transport
in any material and named it as the Dubna
CASCADE code. Average multiplicities of all
particles and light nuclei and their angular as
well as energy spectra are estimated directly
by the code. After including the evaluated and
parameterized data libraries for estimation of
cross sections and the modular structure in the
code [6, 7] the code was published by
Barashenkov [8]. This version of the code was
used for validation of the neutron yield [9, 10]
80 Серия: Физика радиационных повреждений и радиационное материаловедение (94), с. 80-88.
ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 2009. №4-1.
mailto:vkv1951@gmail.com
mailto:vkumarv1@sancharnet.in
in Gamma-2 experiment at JINR.
Subsequently, fission and evaporation models
used in the code were modified by Kumawat
and Barashenkov [11] and recently estimation
of internal flux and radiation dose are also
introduced and tested by making
measurements using the Am+Be kind of
neutron source [12].
In this paper, we have presented results of
simulation of physical quantities of
fundamental interest such as neutron yield,
production of various gases and isotopes by
the CASCADE code in both proton and
neutron collision with the nuclei of material
useful for ADS and compared them as far as
possible with the available experimental data.
Emphasis is laid on the study of neutron
growth by way of (n, xn) reactions at higher
than reactor energies. Cross sections of some
of the (n, xn) reactions being comparable to
fission cross sections and the relationship
between the (n, xn) and fission processes may
affect the design of ADS as the heat
distribution and growth of fission neutrons are
affected. Efforts are made to present the data
of the code in numerical or the graphical mode
so that it may be used in the benchmark study
of the codes.
2. REACTION CROSS SECTIONS
Most of the particle transport codes provide
results of simulation in the form of fractions of
events and they are converted to cross sections
using the data of reaction cross sections.
CASCADE code uses the phase shift analysis
to estimate the reaction and elastic cross
sections. In fact, repeatability of experimental
data of reaction cross sections may be treated
as a test of computation capability the code
more to the case of neutron reaction cross
sections where physics understanding of the
process is some what barred by the non
availability of precision data. Koning et al.
[13] in a detailed study have emphasized
collection of precise reaction cross section data
from the point of design and development of
ADS, study of fusion reactions and the optical
model. In the following Fig. 1 CASCADE
simulation data of non elastic reaction cross
sections for transport of proton and neutron
projectiles in 27Al have been plotted and
compared with the available experimental
data.
101 102 103 104
200
400
600
800
C
S(
N
O
N
) m
b
Ep (MeV)
CASCADE
EXP. DATA [2]
101 102 103 104
200
400
600
800
1000
C
S(
N
O
N
) m
b
En (MeV)
CASCADE
EXP. Data [2]
a b
Fig.1. Comparison of reaction cross sections estimated from CASCADE code with the
experimental data taken from the compilation [2]
Data of p+Al reactions agrees nearly
perfectly and in case of n+Al reaction cross
sections small deviations at high energies may
be because of the fat that the experimental data
is from cosmic rays. This in turn emphasizes
the need of precise accelerator data of neutron
projectile at energy higher than 200 MeV. In
Fig. 2 data of non elastic reaction cross
sections of neutron with different target nuclei
ranging from A=56 to 238 calculated from the
CASCADE code and the optical model code
[14] using Koning’s set of optical model
a) p+Al27 b) n+Al27p+27Al n+27Al
81
parameters (OMP) in its library number 2405
[11] and described in references [15] and [16].
In the optical model calculations are possible
up to 200 MeV and for the purpose of
benchmark study of the CASCADE code we
have presented results up to 1000 MeV.
Results of CASCADE code are in agreement
with the optical model in case of 56Fe and
232Th (OMP are available up to 50 MeV in
case of 232Th) at all energies and small
differences are noticed in case of 208Pb and
209Bi at energies ranging from 40-80 MeV.
One of the useful application of estimation
of non elastic reaction cross sections of p+Al
and n+Al has been made in solving the
problem of non availability of experimental
data of cross sections of monitor reactions of
deuteron projectile, 27Al (d, 3p2n)24Na at
energies >200 MeV. In this energy range many
accelerators that are producing deuteron beam,
there is need of data of cross sections to
monitor the beam flux by activation method.
We have deduced [17] the production cross
sections for the deuteron projectile using the
principle of ‘factorization’ [18] and
CASCADE data for the 27Al (p, 3pn)24Na and
27Al (n, 2p2n)24Na reactions. The deduced
production cross sections of 27Al (d, 3p2n)24Na
reactions are plotted in Fig. 3 along with few
experimental points. Here the fitted curve is
for the CASCADE data. It may be seen that
CASCADE data and the experimental points at
Ed = 2.33 GeV [19] and at E=6 and 7.3 GeV
[20] are in close agreement.
a b
c d
Fig. 2. Non elastic cross sections from the optical model/RIPL [14] at energies 10-200 MeV for
a - 56Fe; b - 208Pb; c - 209Bi and d - 232Th are
compared with that from the CASCADE code
101 102 103
102
103
104
104
C
S
(m
b)
En (MeV)
OMP
CASCADEe56a ) n+F
101 102 103
102
103
OMP
C
S
( m
b
)
En(MeV)
CASCADE
208b) n+Pb
n+208Pb n+56Fe
101 102 103
103
410 OMP
C
S
( m
b
)
En(MeV)
CASCADE
c) n+Bi209n+209Bi
101 102 103
102
103
C
S
( m
b
)
En (MeV)
OMP
CASCADE d) n+Th232
n+232Th
82
102 103 104
0
10
20
30
C
S
( m
b
)
Ed( MeV / n )
Al27(d,x)Na24 at Ed >100MeV/n CASCADE σd (deduced)
EXP.[19-20]
Fig. 3. Production cross sections of
27Al(d, 3p2n)24Na reaction deduced
from the CASCADE data of both
reaction and production reactions
initiated by proton
and neutron in 27Al
.
3. ISOTOPIC CROSS SECTIONS
PRODUCTION
Beam window and target material in the
ADS are irradiated to continuously to the
beam of protons and the fuel material in the
blanket by the produced neutrons give rise to
different highly toxic and/or long lived
isotopes and gases. Study of such isotopes and
gases have attracted attention of
experimentalists [21-24] from the point of
providing data for design and modeling of
ADS. In a paper all data of all materials can
not be presented and we have selected few of
them as representative cases. In Fig.4
production CS of 52Mn (half life 5.591d) in
proton and neutron projectiles colliding with
56Fe material are plotted. In case of p+Fe
collision Michel et al. [24] have presented
similar data from different codes and
experiments and qualitatively CASCADE data
agrees reasonably well at E>50 MeV however,
there is no experimental data available to compare
in case of neutron projectile.
101 102 103 104
10-1
100
101
102
C
S
(m
b)
En (MeV)
CASCADE
b) 26Fe56(n,x)25Mn52
101 102 103 104
10-1
Fig. 4. Production CS of 52Mn in p+56Fe (a) and n+56Fe (b) collision from the
CASCADE code
In Fig. 5 fractional yield of isotope
production in CASCADE in case of 1 GeV
p+208Pb collision has been plotted and in table
production CS of some isotopes of special
interest like some gases and long lived ones
are displayed. According to the CASCADE,
16.5 neutrons are produced in a thin Pb target
in 1 GeV p+Pb collision for which the
100
1
2
10
10
CS
(m
b)
Ep (MeV)
CASCADE
a) 26Fe56(p,2p3n)25Mn52
83
fractional yield is presented then the cross
section of 4He - production per neutron is
555 mb/16.5=33.64 mb/n comparable to
~35 mb/n of the experiment HINDAS [22] of
Ta+p collision in the reverse kinetics. In
column 3 of the table, 4He production in
1 GeV n+Pb collision is also displayed but we
understand that we need to perform
simulations at different neutron energies to
estimate average contribution of 4He
production by the secondary neutron flux
colliding in the Pb target itself. Undoubtedly,
total yield will be more than 555 mb as given
here just for the proton colliding in thin target.
Fig. 5. Fractional isotopic yield in 1 GeV
p+208Pb collision simulated in CASCADE
Production CS of some gases and long lived
isotopes from the cascade code
Product p+Pb n+Pb
1H2 1.31 b 1.240 b
1H3 0.484 b 0.457b
2He3 0.053 b 0.049b
2He4 0.555 b 0.513b
146Sm62 (T1/2= 108 y) 0.054 b 0.036
151Sm62 (T1/2=73 y) 0.006 b -
148Gd64 (T1/2=74.6 y) 0.243 b 0.296
150Gd64(T1/2=1.8·106y) 0.18 b 0.152
154Dy66 (T1/2 = 3·106 y) 0.548 b 0.727
0 10 20 30 40 50 60 70 80
10-7
10-6
10-5
10-4
10-3
10-2
10-1
100
Fr
ac
tio
na
l Y
ie
ld
1GeV+Pb
4. (n, xn) REACTIONS
So far there is very little experimental data
is available for the (n, xn) reactions and it is
understandable that they may play important
role in a hybrid system. Secondly, this area of
study combines the areas of isotopic and
neutron yield in the environment of high
energy neutrons. In this situation, we have
simulated these reactions by CASCADE code
in case of Bi209 target and compared them with
the experimental data of Kim et al. [25] in
Fig. 6. The two data at x>3 are in agreement
and both show existence of even-odd effect in
209Bi [26].
In the following Fig. 7, CS are plotted for
(n, xn) reactions with 52Cr and 232Th targets to
show another evidence of the even-odd effect
in even A nuclei as seen in case of odd A
nucleus like 209Bi in Fig. 6. Even-odd
structures have been predicted in de-excitation
code ABLA07 [26] in case of light particle
emission in high energy nucleus + nucleus
collision.
In the following Fig. 8 we have plotted
cross sections of (n,xn) reactions with respect
to xn neutrons produced in case of different
energy neutrons with a) 91Zr and b) 98Mo and
c) 181Ta targets. It may be noted that with the
increase of energy xn increases differently for
different target masses and in case of high
mass nuclei cross section of producing same
number of neutrons (xn) is lower for higher
energy. Average number of neutrons in pure
(n, xn) for x=1,2,3… reactions, <n(xn)> is
compared with the total number of neutrons in
the given reaction, <n> in the form of the ratio,
<n(xn)>/<n> and plotted with the projectile
energy in Fig. 9 for the three categories of
materials i) light, ii) heavy but non fuel and
iii) fuel nuclei of the ADS material.
102
103
CASCADE
b)
CASCADE
Kim et al. [25]
a) 32.8 MeV n+Bi
1
102
b ) 97MeV n+Bi Kim et al.[25]
84
)b
Fig. 6. CASCADE data of cross sections of 209Bi(n, xn) reactions at: a - 32.8 MeV,
b
Fig. 8. Production cross section versus number of ne
2 4 6 8 10 12
– 97 MeV, c - 132 MeV, and d - 147 MeV energy compared with experimental data
by E. Kim et al. [25]
Fig. 7. Cross sections of (n, xn) reactions in even A nuclei: a - 52Cr and b - 232Th
utrons in (n, xn) reactions at energies
ranging from 11 to 1000 MeV for: a - 91Zr, b - 98Mo
101
102
C
S
(m
b)
Xn
CASCADE
Kim et al.[25]
c ) 132 MeV n+Bi
0 2 4 6 8 10 1 2 14 1 6 18
10 0
10 1
10 2
C A S C A D Ed ) 147 M e V n + B i
C
S
( m
b
)
X n
K im e t a l.[25 ]
1 2 3 4
100
200
300
400
500
600
700
C
S
(m
b)
Xn
En(20MeV)
En(50MeV)
a) Cr52
0 2 4 6 8 10
100
200
300
400
500
600
C
S
(m
b)
Xn
En (50MeV)
b) Th232
102
103 c ) n+Ta181
b)
E eV11M
E14
E20
E30
E50
E70
E100
E150
0 1 2 3 4 5 6 7 8 9 10
10-4
10-3
10-2
10-1
100
101
102
103
cr
os
s
se
ct
io
n(
m
b)
Xn
E11MeV
E15
E20
E30
E50
E70
E100
E200
E300
E500
E700
E1000
0 1 2 3 4 5 6 7 8 9 10
101
102
103
a) Zr91
cr
os
s
se
ct
io
n(
m
b)
Xn
E11MeV
E15
E20
E30
E50
E70
E100
E200
E300
E500
E700
E1000
96b ) Mo
b) Mo98
85
Fig. 8. Production cross section versus number of neutrons in (n, xn)
he curves are drawn to guide the eyes. It
ca
is more fissionable. Although this fact needs
Fig. 9. Percentage contribution of (n, xn) r actions in neutron production by different
101 102 103
reactions at energies ranging from 11 to 1000 MeV
for 181Ta (c)
T
n be pointed out that the percentage
contribution of (n,xn) reactions in case of fuel
nuclei does not show any clubbing like that in
the other two cases (where it is independent of
the material of the category) and percentage
contribution of (n, xn) reactions at high
energies decreases as 233U<238U<232Th. Thus,
Thorium is more prone to neutron
multiplication by the (n, xn) reaction and 233U
experimental validation yet on its face it
appears important from the point of settling
down the question of combinations of fuel
elements of ADS. It is expected that it will
have noticeable effect on the heat distribution
also. The detailed study of (n, xn) reactions
may prove important from the point of settling
down the combinations of fuel elements for
ADS and the heat distribution.
e
ADS material nuclei as function of neutron energy
10
20
30
40
50
60
70
80
90
100 C r52C om parison of light, non fue l and fue l e lem ents
Fe56
W 184
<n
,x
n>
/<
n>
(%
)
E n (M eV)
Pb208
Th232
U 233
U 238
86
5. DISCUSSIONS
AND CONCLUSIONS
We have presented the CASCADE data for
some selective nuclei and energy because of
the limitations of space and in the readable
graphical format for their comparison with
other codes and experiments for the sake of
benchmarking. It may be inferred that data of
the reaction cross sections agrees with the
experimental data as well as the models of
fundamental interest such as optical model.
Similarly, the data of production cross sections
agrees well with the experiments. It may
however be stressed that more precise neutron
data is required to improve the code in case of
reactions with neutron as a projectile. In
respect of isotope data from the code there is
need to introduce the concept of cumulative
yield in the code so that its results may be
compared with the experimental
measurements.
From the present study of (n, xn) reactions
the code results show presence of even-odd
effect and other interesting results as in Fig. 9
which may help in selection of combinations
of fuel elements for ADS logically. For both
the cases, a more detailed study is required to
be carried out from the simulation codes and
experimentally with emphasis to the fuel
elements.
For the study of effects of radiation
damage, it may be mentioned that the present
version of the code provides data of energy
distributions of neutrons, protons and light
charge particles such as d, t, 3He and 4He and it
is not difficult to know such distributions of
heavier secondary nuclei if required. However,
presently the code gives average kinetic
energies of all isotopes along with their
production cross sections which is also useful
for calculation of total radiation damage with
the help of low energy codes like TRIM or
IOTA. Efforts can be made to develop a
unified code of high energy and low energy
transport of all radiations produced in a beam
transport in a medium.
Acknowledgements: Authors acknowledge
thanks to BRNS (DAE), India for the grants
for project and author (VK) is grateful to the
IAEA, Vienna for financial support for his
participation in Technical Meeting-34567 at
Kharkov.
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ИЗУЧЕНИЕ МАТЕРИАЛА СУБКРИТИЧЕСКОЙ СИСТЕМЫ,
ВОЗБУЖДАЕМОЙ УСКОРИТЕЛЕМ, С ПОМОЩЬЮ
ПРОГРАММЫ CASCADE
В. Кумар, Х. Кумават, Читра Бхатиа
При существующем положении дел с экспериментальными данными, требующимися
для проектировки и моделирования ADS (accelerator driven systems) и для других
аналогичных применений, становятся важными разработка и эталонное тестирование
программ моделирования для обеспечения получения надежных данных. Из программ,
существующих для внутриядерных каскадов, программа CASCADE, достоверность
которой проверялась для рождения нейтронов при столкновениях протонов с
материалами, имевшими в прошлом высокий атомный номер Z, использовалась для
изучения ядерного поведения некоторых известных материалов ADS (Th, U, Pb, Bi, W, Fe,
Cr и Al) в отношении сечений реакций и сечений рождения изотопов и нейтронов в
широком интервале энергий от 11 МэВ до нескольких гигаэлектронвольт. Особое
внимание уделялось данным о сечениях реакций (n, xn). Найдено, что они играют
определяющую роль при выборе сочетаний топлива. Программа дает данные о
нейтронных сечениях, которые находятся в согласии с существующими
экспериментальными данными, при этом подчеркивается необходимость дальнейшей
проверки с использованием точных данных от ускорителей.
ВИВЧЕННЯ МАТЕРІАЛУ СУБКРИТИЧНОЇ СИСТЕМИ,
ЩО ЗБУДЖУЄТЬСЯ ПРИСКОРЮВАЧЕМ ЗА ДОПОМОГОЮ
ПРОГРАМИ CASCADE
В. Кумар, Х. Кумават, Читра Бхатіа
За існуючого стану справ з експериментальними даними, які необхідні для
проектування та моделювання АDS (accelerator driven systems) і для інших аналогічних
застосувань, важливими стають розробка та еталонне тестування програм моделювання
для забезпечення отримання надійних даних. Із програм, що існують для
внутрішньоядерних каскадів, програма CASCADE, достовірність якої перевірялась для
народження нейтронів при зіткненні протонів з матеріалами, що мали в минулому
високий атомний номер Z, використовувалась для вивчення ядерної поведінки деяких
відомих матеріалів ADS (Th, U, Pb, Bi, W, Fe, Cr, Al) у відношенні перетинів реакцій та
перетинів народження ізотопів і нейтронів у широкому інтервалі енергій від 11 МеВ до
кількох гігаелектронвольт. Особлива увага приділялась даним щодо перeтинів реакцій (n,
xn). Встановлено, що вони грають визначну роль при виборі сполучень палива. Програма
забезпечує дані щодо нейтронних перетинів, які узгоджуються з існуючими
експериментальними даними, при цьому підкреслюється необхідність подальшої
перевірки з використанням точних даних від прискорювача.
88
|
| id | nasplib_isofts_kiev_ua-123456789-96339 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-07T18:42:48Z |
| publishDate | 2009 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Kumar, V. Kumawat, H. Chitra Bhatia 2016-03-15T10:04:11Z 2016-03-15T10:04:11Z 2009 A study of accelerator driven sub critical system - material using the CASCADE code / V. Kumar, H. Kumawat, Chitra Bhatia // Вопросы атомной науки и техники. — 2009. — № 4. — С. 80-88. — Бібліогр.: 26 назв. — англ. 1562-6016 https://nasplib.isofts.kiev.ua/handle/123456789/96339 In the existing situation of experimental data required for design and modeling of ADS and
 similar other applications, development and benchmarking of the simulation codes for providing
 reliable data has become essential. Amongst the intra nuclear cascade codes, CASCADE code
 which has been validated for the neutron production in proton collision with the high Z materials
 in the past, has been used to study nuclear behavior of some of the prominent ADS materials
 like, Th, U, Pb, Bi, W, Fe, Cr and Al in respect of reaction and production cross sections of
 isotopes and neutrons in a wide range of energy, 11 MeV to several GeV. Emphasis has been
 laid on the data of cross sections of (n, xn) reactions. It is found that their role is definite and
 effective in deciding fuel combinations. The code provides neutron cross section data which
 shows agreement with the existing experimental data and stresses need of further validation
 using precision data from the accelerators. За існуючого стану справ з експериментальними даними, які необхідні для
 проектування та моделювання АDS (accelerator driven systems) і для інших аналогічних
 застосувань, важливими стають розробка та еталонне тестування програм моделювання
 для забезпечення отримання надійних даних. Із програм, що існують для
 внутрішньоядерних каскадів, програма CASCADE, достовірність якої перевірялась для
 народження нейтронів при зіткненні протонів з матеріалами, що мали в минулому
 високий атомний номер Z, використовувалась для вивчення ядерної поведінки деяких
 відомих матеріалів ADS (Th, U, Pb, Bi, W, Fe, Cr, Al) у відношенні перетинів реакцій та
 перетинів народження ізотопів і нейтронів у широкому інтервалі енергій від 11 МеВ до
 кількох гігаелектронвольт. Особлива увага приділялась даним щодо перeтинів реакцій (n,
 xn). Встановлено, що вони грають визначну роль при виборі сполучень палива. Програма
 забезпечує дані щодо нейтронних перетинів, які узгоджуються з існуючими
 експериментальними даними, при цьому підкреслюється необхідність подальшої
 перевірки з використанням точних даних від прискорювача. При существующем положении дел с экспериментальными данными, требующимися
 для проектировки и моделирования ADS (accelerator driven systems) и для других
 аналогичных применений, становятся важными разработка и эталонное тестирование
 программ моделирования для обеспечения получения надежных данных. Из программ,
 существующих для внутриядерных каскадов, программа CASCADE, достоверность
 которой проверялась для рождения нейтронов при столкновениях протонов с
 материалами, имевшими в прошлом высокий атомный номер Z, использовалась для
 изучения ядерного поведения некоторых известных материалов ADS (Th, U, Pb, Bi, W, Fe,
 Cr и Al) в отношении сечений реакций и сечений рождения изотопов и нейтронов в
 широком интервале энергий от 11 МэВ до нескольких гигаэлектронвольт. Особое
 внимание уделялось данным о сечениях реакций (n, xn). Найдено, что они играют
 определяющую роль при выборе сочетаний топлива. Программа дает данные о
 нейтронных сечениях, которые находятся в согласии с существующими
 экспериментальными данными, при этом подчеркивается необходимость дальнейшей
 проверки с использованием точных данных от ускорителей. Authors acknowledge thanks to BRNS (DAE), India for the grants for project and author (VK) is grateful to the IAEA, Vienna for financial support for his participation in Technical Meeting-34567 at Kharkov. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники A study of accelerator driven sub critical system - material using the CASCADE code Вивчення матеріалу субкритичної системи, що збуджується прискорювачем за допомогою програми CASCADE Изучение материала субкритической системы, возбуждаемой ускорителем, с помощью программы CASCADE Article published earlier |
| spellingShingle | A study of accelerator driven sub critical system - material using the CASCADE code Kumar, V. Kumawat, H. Chitra Bhatia |
| title | A study of accelerator driven sub critical system - material using the CASCADE code |
| title_alt | Вивчення матеріалу субкритичної системи, що збуджується прискорювачем за допомогою програми CASCADE Изучение материала субкритической системы, возбуждаемой ускорителем, с помощью программы CASCADE |
| title_full | A study of accelerator driven sub critical system - material using the CASCADE code |
| title_fullStr | A study of accelerator driven sub critical system - material using the CASCADE code |
| title_full_unstemmed | A study of accelerator driven sub critical system - material using the CASCADE code |
| title_short | A study of accelerator driven sub critical system - material using the CASCADE code |
| title_sort | study of accelerator driven sub critical system - material using the cascade code |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/96339 |
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