Research of transmutation of products of nuclear cycle at the electron accelerator
The analysis of the use of linear electron accelerators for transmutation of fission products and actinides from nuclear power plants is carried out. The results of irradiation of isotopes ⁹⁰Sr, ²⁴¹Am and ChNPP fuel containing materials with the neutron flow from the linac are described. The var...
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irk-123456789-790742015-03-26T03:02:05Z Research of transmutation of products of nuclear cycle at the electron accelerator Dikiy, N.P. Dovbnya, A.N. Lyashko, Yu.V. Uvarov, V.L. Применение ускоренных пучков The analysis of the use of linear electron accelerators for transmutation of fission products and actinides from nuclear power plants is carried out. The results of irradiation of isotopes ⁹⁰Sr, ²⁴¹Am and ChNPP fuel containing materials with the neutron flow from the linac are described. The variant of the test stand for investigation of transmutation of fission products and actinides is proposed on the basis of the powerful linear electron accelerator. Проведено аналіз використання лінійних прискорювачів електронів для трансмутації продуктів ділення й актиноїдів атомних електростанцій. Описано результати опромінення потоком нейтронів на ЛПЕ ізотопів ⁹⁰Sr, ²⁴¹Am і паливовміщуючих мас ЧАЕС. Запропоновано варіант стенда для дослідження трансмутації продуктів ділення й актиноїдів на базі потужного лінійного прискорювача електронів. Проведен анализ использования линейных ускорителей электронов для трансмутации продуктов деления и актиноидов атомных электростанций. Описаны результаты облучения потоком нейтронов на ЛУЭ изотопов ⁹⁰Sr, ²⁴¹Am и топливосодержащих масс ЧАЭС. Предложен вариант стенда для исследования трансмутации продуктов деления и актиноидов на базе мощного линейного ускорителя электронов. 2004 Article Research of transmutation of products of nuclear cycle at the electron accelerator / N.P. Dikiy, A.N. Dovbnya, Yu.V. Lyashko, V.L. Uvarov // Вопросы атомной науки и техники. — 2004. — № 1. — С. 203-205. — Бібліогр.: 5 назв. — англ. 1562-6016 PACS: 29.17.+w, 28.41Kw http://dspace.nbuv.gov.ua/handle/123456789/79074 en Вопросы атомной науки и техники Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
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Применение ускоренных пучков Применение ускоренных пучков |
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Применение ускоренных пучков Применение ускоренных пучков Dikiy, N.P. Dovbnya, A.N. Lyashko, Yu.V. Uvarov, V.L. Research of transmutation of products of nuclear cycle at the electron accelerator Вопросы атомной науки и техники |
| description |
The analysis of the use of linear electron accelerators for transmutation of fission products and actinides from
nuclear power plants is carried out. The results of irradiation of isotopes ⁹⁰Sr, ²⁴¹Am and ChNPP fuel containing
materials with the neutron flow from the linac are described. The variant of the test stand for investigation of
transmutation of fission products and actinides is proposed on the basis of the powerful linear electron accelerator. |
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Article |
| author |
Dikiy, N.P. Dovbnya, A.N. Lyashko, Yu.V. Uvarov, V.L. |
| author_facet |
Dikiy, N.P. Dovbnya, A.N. Lyashko, Yu.V. Uvarov, V.L. |
| author_sort |
Dikiy, N.P. |
| title |
Research of transmutation of products of nuclear cycle at the electron accelerator |
| title_short |
Research of transmutation of products of nuclear cycle at the electron accelerator |
| title_full |
Research of transmutation of products of nuclear cycle at the electron accelerator |
| title_fullStr |
Research of transmutation of products of nuclear cycle at the electron accelerator |
| title_full_unstemmed |
Research of transmutation of products of nuclear cycle at the electron accelerator |
| title_sort |
research of transmutation of products of nuclear cycle at the electron accelerator |
| publisher |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
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2004 |
| topic_facet |
Применение ускоренных пучков |
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http://dspace.nbuv.gov.ua/handle/123456789/79074 |
| citation_txt |
Research of transmutation of products of nuclear cycle at the electron accelerator / N.P. Dikiy, A.N. Dovbnya, Yu.V. Lyashko, V.L. Uvarov // Вопросы атомной науки и техники. — 2004. — № 1. — С. 203-205. — Бібліогр.: 5 назв. — англ. |
| series |
Вопросы атомной науки и техники |
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AT dikiynp researchoftransmutationofproductsofnuclearcycleattheelectronaccelerator AT dovbnyaan researchoftransmutationofproductsofnuclearcycleattheelectronaccelerator AT lyashkoyuv researchoftransmutationofproductsofnuclearcycleattheelectronaccelerator AT uvarovvl researchoftransmutationofproductsofnuclearcycleattheelectronaccelerator |
| first_indexed |
2025-07-06T03:10:39Z |
| last_indexed |
2025-07-06T03:10:39Z |
| _version_ |
1836865489712709632 |
| fulltext |
RESEARCH OF TRANSMUTATION OF PRODUCTS OF NUCLEAR
CYCLE AT THE ELECTRON ACCELERATOR
N.P. Dikiy, A.N. Dovbnya, Yu.V. Lyashko, V.L. Uvarov
NSC KIPT, Kharkov, Ukraine;
ndikiy@kipt.kharkov.ua
The analysis of the use of linear electron accelerators for transmutation of fission products and actinides from
nuclear power plants is carried out. The results of irradiation of isotopes 90Sr, 241Am and ChNPP fuel containing
materials with the neutron flow from the linac are described. The variant of the test stand for investigation of
transmutation of fission products and actinides is proposed on the basis of the powerful linear electron accelerator.
PACS: 29.17.+w, 28.41Kw
INTRODUCTION
Research of waste management by the technologies
and their practical implementation under optimum
safety conditions continues to be active. Together with
disposal in geological rocks a promising direction in
solving the problems of the waste manipulation is the
use of transmutation.
In this connection the new approaches to reducing
the waste recycling are developed. As is known at low
concentration of neutrons in the reactor the operating
time of isotopes of the higher nuclear weight in the first
approximation equal to [1]:
NA=((σA-1⋅No⋅n⋅v)/(n⋅v(σA-1+σf)+λA)) ×
× (1−exp(−n⋅v(σA-1+σf)−λA)⋅t)
No, NA are the content of nuclei with atomic number А−
1 and А, σA−1, σf are the cross-section of neutron-
capture and fission for nuclei with atomic numbers А-1
and A, respectively, n is concentration of neutrons, v is
average neutron speed, λA is decay constant of nuclei
with atomic number A.
Table 1. Equilibrium distribution of transuranium elements at high dozes in the reactor on thermal and fast neutrons
(on the left) and the charge of neutrons Dj on division (Dj < 0 means the excess of own manufacture n, Dj > 0 means
the necessity of an external source of neutrons)
Isotope Thermal n
spectrum
Fast n
spectrum
237Np 5.51 0.75
238Pu 4.17 0.89
239Pu 23.03 66.75
240Pu 10.49 24.48
241Am 0.54 0.97
241Pu 9.48 2.98
242Cm 0.18 0.40
242mAm 0.02 0.07
242Pu 3.89 1.8
243Am 8.11 0.44
243Cm 0.02 0.03
244Cm 17.85 0.28
245Cm 1.27 0.07
246Cm 11.71 0.03
247Cm 0.75 2.E-3
248Cm 2.77 6.E-4
249Bk 0.05 1.E-5
250Cf 0.03 7.E-6
251Cf 0.02 9.E-7
252Cf 0.08 4.E-8
Total 100.0 100.0
Values Dj (neutron consumption per fission)
Isotope (or fuel type)
1015
n/cm2
fast n
1014 n/cm2,
n of PWR
1016
n/cm2,
n of
PWR
1016 n/cm2,
highly
thermalized
Th with extraction of
238Pa
-0.39 -0.24 -0.24 -0.27
Th without extraction
of 238Pa
-0.38 0.20 1.22 1.14
238U -0.62 0.07 0.05 0.1
238Pu -1.36 0.17 0.042 -0.13
239Pu -1.46 -0.67 -0.79 -1.07
240Pu -0.96 0.44 0.085 0.14
241Pu -1.24 -0.56 -0.91 -0.86
242Pu -0.44 1.76 1.10 1.12
237Np -0.59 1.12 0.53 -0.463
241Am -0.62 1.12 0.076 -0.54
243Am -0.60 0.82 0.16 0.21
244Cm -1.39 -0.15 -0.53 -0.48
245Cm -2.51 -1.48 -1.46 -1.37
DTRU (discharge from
a PWR)
-1.17 -0.05 -0.35 -0.54
DTRU+Pu+Np (discharge
from a PWR)
-0.70 1.1 0.3 0.4
As is seen, during the reactor operating time the
content of elements with a large A decreases with
neutron concentration increasing. Therefore the increase
of neutron flow density in the reactor results in the
change of the actinide content in the reactor.
The approach ADS (Accelerator Driven Systems)
has many supporters in the world. The main advantage
of ADS is the significant decrease of fission products
and TRU, and also burning out of new transuraniums.
The second feature of ADS is repeated recirculation of
___________________________________________________________
PROBLEMS OF ATOMIC SIENCE AND TECHNOLOGY. 2004. № 1.
Series: Nuclear Physics Investigations (42), p.203-205. 203
mailto:ndikiy@kipt.kharkov.ua
fuel or waste. It allows one to essentially reduce the
danger of the spent fuel from usual nuclear power plants
after updating with the help of ADS (tabl.1 (on the
left)).
From table 1 (on the right) it can be seen that for fast
neutrons the flow 1015 n/s⋅sm2 practically completely
results in burning out of transuraniums. Their
radiotoxicity is prevalent. From table 2 it is seen that
asymptotic spectra lead to isotopes with А>238 with the
result being more acceptable by toxicity. Therefore,
third advantage of ADS systems is the fast neutron
spectrum. As is seen from the given tables during
operating time the low level of transuranium elements
and fission products in reactors with a flow 1015 n/s sm2
on fast neutrons is attained. The projects of use of
powerful linear proton accelerators [2] and deuteron
accelerators [3] are known. The use of linear electron
accelerators for transmutation is promising [4].
The plutonium isotopes contribute for about 90% to
the radiotoxic inventory, the rest 10% is contributed by
americium and curium. In the high-level waste arising
from reprocessing activities, during which 99.88% of
the plutonium and uranium are recovered, americium
and curium are the main contributors. To reach a
considerable reduction of the radiotoxicity, at least 90%
of the americium is need to be fissioned. This can be
achieved by multiple recycling in fast neutron flux or
once-via transmutation in high-thermal or epidermal
neutron flux.
Spectrum of gamma radiation from the sample 241Am after irradiation with neutrons for one year
RESULTS AND DISCUSSION
Samples of 241Am, 90Sr and FCM 4 block ChNPP
were investigated. The irradiation of samples was
carried out by neutrons from the aluminium-silicon
converter during year [5]. The irradiation time was 2⋅
107 s. Through the target 4⋅1014 neutrons penetrated. The
estimated neutron fluence was 5⋅1018 neutrons/cm2. The
instant flow of neutrons is about 1013 n/s cm2. In the
sample 90Sr the activity 89Sr caused by the nuclear
reaction 90Sr(n,2n)89Sr was detected. The low yield of
radiation with an energy of 1210 keV did not allowed to
measure the content of 91Sr → 91Y (reaction 90Sr(n,γ)91Sr,
Ires = 0,3 b). The spectrum of gamma radiation from the
sample 241Am is given in Fig. In the sample 241Am the
activity of isotopes 238, 239Np, 233Pa, 241, 243Am is detected.
The radiation of fission products of 103Ru, 154Eu, 95Nb
and isotopes 57, 60Co, 59Fe, 51Cr caused by the activity of
a material of the container is detected. Besides the traces
of isotopes of americium, the isotopes of europium-154
were observed.
The feature of irradiation of samples from FCM
4 block ChNPP during year is the absence of fission
products of 103Ru, 95Nb.
The powerful linear electron accelerator (Р=20 kw
in the beam) can be the tool for the study of
transmutation of fission products and actinides. 2 1013
n/s from the tantalum converter when using the water
moderator will have a maximum of distribution of a
neutron flow nv at a distance from the centre of a beam
of about 7.6 cm. With the use of the moderator with low
cross-section of capture (D2O) the fast neutron flow (≈
1…5 eV) in a maximum will have 1015 n/s⋅cm2, that
allows one to solve the majority of research tasks on the
management with the spent fuel of nuclear power
plants.
Table 2. Radiotoxicity of isotopes (CD=Cancer Dose Hazard)
204
0 500 1000 1500
1E1
1E2
1E3
1E4
0 2 4 6 8 10
0
2
4
6
8
10
co
u
n
ts
number of channel
154
Eu
60
Co
238
Np
154
Eu
239
Np
239
Np
239
Np
241
Am
241
Am
511 keV
54
Mn
58
Co
Isotope
Toxicity
factor
CD/Ci
Half-life,
years
Toxicity
factor CD/g
210Pb 455 22.3 34800
223Ra 15.6 0.03 799000
226Ra 36.3 1.6⋅103 35.9
227Ac 1185 21.8 85800
229Th 127.3 7.3⋅103 27.2
230Th 19.1 7.54⋅104 0.394
231Pa 372 3.28⋅104 0.176
2 34U 7.59 2.46⋅105 0.047
235U 7.23 7.04⋅108 1.56⋅10−5
236U 7.5 2.34⋅107 4.85⋅10−4
238U 6.97 4.47⋅109 2.34⋅10−6
237Np 197.2 2.14⋅106 0.139
238Pu 246.1 87.7 4220
239Pu 267.5 2.41⋅104 16.6
240Pu 267.5 6.56⋅103 60.8
242Pu 267.5 3.75⋅105 1.65
241Am 272.9 433 936
242mAm 267.5 141 28000
243Am 272.9 7370 54.5
Isotope
Toxicity
factor CD/Ci
Half-life,
years
Toxicity factor
CD/g
242Cm 6.9 0.45 22900
243Cm 196.9 29.1 9960
244Cm 163 18.1 13200
245Cm 284 8500 48.8
246Cm 284 4800 86.7
Shot-lived Fission Products
90Sr 16.7 29.1 2280
90Y 0.6 0.0073 326000
137Cs 5.77 30.2 499
Long-lived Fission Products
99Tc 0.17 2.13⋅105 2.28⋅10−3
129I 64.8 1.57⋅107 0.0115
93Zr 0.095 1.5⋅106 2.44⋅10−4
135Cs 0.84 2.3⋅106 9.68⋅10−4
14C 0.2 5.93⋅103 0.892
59Ni 0.08 7.6⋅104 6.38⋅10−3
63Ni 0.03 100 1.7
126Sn 1.7 1⋅105 0.0483
REFERENCES
1. Nuclear astrophysics. Cambridge: Cambridge
University Press, 1982, p.519.
2. C.Rubbia Status of the Energy Amplifier Concept
Proc. // Of the Int. Conf. On Accelerator Driven
Technology and Aplication, Kalmar, Sweden, 1996,
p.35.
3. R.Soule et al. The MUSE experiments for sub-critical
neutronics validation // 6th Int. Exchange Meeting on
P&T, Madrid, Spain, 11-13 December 2000, OECD
Energy Agency, Paris, France, 2001.
4. M.A.Reda, F.Harmon, I.D.Pocatello, S.B.Sedineni A
Photo-neutron Source for a Sub-Critical Nuclear
Reactor Programs // Proc. Of University of Nevada,
Las Vegas N.V. APS (Accelerators Driven Sub-
Critical Systems), p. 101-105.
5. R.J.M.Konings, R.Conrad, G.Dassel, B.J.Pijlgroms et
al The EFTTRA-T4 experiment on 241Am
transmutation // Jour. Nucl. Mat. 2000, v. 282,
p. 159-170.
ИССЛЕДОВАНИЕ ТРАНСМУТАЦИИ ПРОДУКТОВ ЯДЕРНОГО ЦИКЛА
НА УСКОРИТЕЛЕ ЭЛЕКТРОНОВ
Н.П. Дикий, А.Н. Довбня, Ю.В. Ляшко, В.Л. Уваров
Проведен анализ использования линейных ускорителей электронов для трансмутации продуктов деления
и актиноидов атомных электростанций. Описаны результаты облучения потоком нейтронов на ЛУЭ
изотопов 90Sr, 241Am и топливосодержащих масс ЧАЭС. Предложен вариант стенда для исследования
трансмутации продуктов деления и актиноидов на базе мощного линейного ускорителя электронов.
ДОСЛІДЖЕННЯ ТРАНСМУТАЦІЇ ПРОДУКТІВ ЯДЕРНОГО ЦИКЛУ
НА ПРИСКОРЮВАЧІ ЕЛЕКТРОНІВ
М.П. Дикий, А.М .Довбня, Ю.В. Ляшко, В.Л. Уваров
Проведено аналіз використання лінійних прискорювачів електронів для трансмутації продуктів ділення й
актиноїдів атомних електростанцій. Описано результати опромінення потоком нейтронів на ЛПЕ ізотопів
90Sr, 241Am і паливовміщуючих мас ЧАЕС. Запропоновано варіант стенда для дослідження трансмутації
продуктів ділення й актиноїдів на базі потужного лінійного прискорювача електронів.
___________________________________________________________
PROBLEMS OF ATOMIC SIENCE AND TECHNOLOGY. 2004. № 1.
Series: Nuclear Physics Investigations (42), p.203-205. 205
INTRODUCTION
RESULTS AND DISCUSSION
REFERENCES
Н.П. Дикий, А.Н. Довбня, Ю.В. Ляшко, В.Л. Уваров
М.П. Дикий, А.М .Довбня, Ю.В. Ляшко, В.Л. Уваров
|