Development of new trends in applied nuclear physics with the use of high-energy braking radiation
A review is given about investigation in nuclear medicine, atomic energetics (Chernobyl problem including), geology etc. that carried out in the NSC KIPT mainly during last decade on the basis of home made electron linacs. Дано огляд досліджень в області ядерної медицини, атомної енергетики (включаю...
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| citation_txt | Development of new trends in applied nuclear physics with the use of high-energy braking radiation / N.P. Dikiy, A.N. Dovbnya, V.L. Uvarov // Вопросы атомной науки и техники. — 2003. — № 2. — С. 99-102. — Бібліогр.: 31 назв. — англ. |
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| description | A review is given about investigation in nuclear medicine, atomic energetics (Chernobyl problem including), geology etc. that carried out in the NSC KIPT mainly during last decade on the basis of home made electron linacs.
Дано огляд досліджень в області ядерної медицини, атомної енергетики (включаючи проблему Чорнобиля), геології і т.д., що проводилися в ННЦ ХФТІ головним чином протягом останніх 10 років на основі лінійних прискорювачів електронів власного виробництва.
Дан обзор исследований в области ядерной медицины, атомной энергетики (включая проблему Чернобыля), геологии и т.д., проводившихся в ННЦ ХФТИ главным образом в течение последних 10 лет на основе линейных ускорителей электронов собственного производства.
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A P P L I C A T I O N O F T H E N U C L E A R M E T H O D S
DEVELOPMENT OF NEW TRENDS IN APPLIED NUCLEAR PHYSICS
WITH THE USE OF HIGH-ENERGY BRAKING RADIATION
N.P. Dikiy, A.N. Dovbnya, V.L. Uvarov
National Science Center “Kharkov Institute of Physics and Technology”, Kharkov, Ukraine
e-mail: uvarov@kipt.kharkov.ua
A review is given about investigation in nuclear medicine, atomic energetics (Chernobyl problem including),
geology etc. that carried out in the NSC KIPT mainly during last decade on the basis of home made electron linacs.
PACS: 84.40.Cb. 81.70.-q. 87.58.Ji
INTRODUCTION
History of creation of the electron linacs in the NSC
KIPT for investigation in nuclear physics is inseparably
linked with the endeavour to apply these facilities in dif-
ferent branches of the science & technology. First of all,
it were some investigations in nuclear medicine & bio-
logy [1,2], dosimetry [3] etc. During last decade owing
to commissioning a number of accelerators [4, 5] some
new trends have been developed with the use of high-
power braking radiation: elaboration of safe for ecology
(“soft”) technologies of isotopes production (mainly
medical ones), characterization of radioactive waste
(RAW) and radiation testing of perspective materials
and structures for immobilization (disposal) of long-
lived RAW, gamma-activation analysis etc. The short
survey of some obtained results is given in the paper.
1. ELABORATION OF SOFT TECHNOLO-
GIES FOR ISOTOPES PRODUCTION
1.1. Nowadays the basic methods for isotope produc-
tion include nuclear reactions under effect of heavy
particles (mainly neutrons and protons) generated in the
reactors and accelerators. Although the cross-sections of
such reactions are essentially higher than photonuclear
ones, however the heavy charged particle interacting
with the target material looses rapidly its energy and
leaves the resonance region. So, the efficiency of the
isotope production (isotope nuclei generation rate per
unit of the beam power) on the heavy particle accelerat-
ors is not very high.
In case of reactors a great amount of the RAW ac-
companying the useful isotope production constitutes a
problem. For example, while generating 1Ci of 99Mo
(parent-isotope for 99mTc - one of the most widely used
nuclide for medical diagnostics) on a reactor is up to 50
Ci of long-lived waste produced parallelly.
Thus, taking into account a continuous growth of the
medical isotopes utilization, the elaboration of secure
technologies for their manufacturing is a problem of ex-
treme importance.
For production of some medical & biophysical iso-
topes it is possible to use a braking radiation of the elec-
tron accelerator. In this case the generation efficiency is
significantly higher than one by using heavy charged
particles and neutrons in spite of the relatively low spe-
cific activity of produced isotope (≤1Ci/g) [6]. Besides,
isotope manufacturing using an electron accelerator is
accompanied by much less amount of RAW comparison
with another known technologies.
Characteristics of some isotopes, which are used in
nuclear medicine and promising for manufacturing on
electron accelerator, are shown in Table 1.
1.2. The effective production of isotopes is possible
only by providing a large particle flux. Therefore the
different versions of design of the converter assembly
were investigated as the first stage of technology elabor-
ation. As the criterions of optimisation there were
chosen the maximum of the conversion coefficient in
the range of braking photons energy corresponding to
photonuclear reactions, capability of effective heat re-
jection, and also maximum absorption of primary elec-
trons in the converter to decrease a heat load on the tar-
get. To solve this problem the computer simulation was
carried out in 2D-geometry relative to the axis of the
electron beam on the basis of GEANT package supple-
mented with the data on cross-sections of corresponding
photonuclear reactions [7].
Taking into account the obtained outcomes we have
fulfilled the calculations for generation of different iso-
topes with the converter unit consisted of two tantalum
plates separated by 3 mm water layers. It was supposed
as well that the infinite layer with thickness of 10 mm
from a given material of natural isotope composition is
placed as a target 10 mm apart behind the converter.
Results of the calculations made in such geometry are
listed in Table 2. It presents the data for a relative yield
of generated isotope Y1 (recalculated per 1 primary elec-
tron), activity of the isotope A, produced per one operat-
ing day for a beam current 1 mA, and also a beam
power P absorbed in the target at the optimum regime of
irradiation (E=25 MeV).
As one can see from the obtained outcomes it is pos-
sible an effective production different radionuclides us-
ing high-current electron accelerator. The indispensable
conditions of such manufacturing are beam parameters
control on the converter & target setup and the ensuring
of its continuous cooling.
1.3. The experimental study of regularities of the
99Mo/99mTc generation using the targets of different
phase composition was carried out [8] and experimental
samples of 99mTc as well as 57Co-sources for calibration
of gamma-chambers were produced and tested [9-11]. A
possibility of production of other isotopes using electron
accelerators was investigated also [12,13].
PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. 2003, № 2.
Series: Nuclear Physics Investigations (41), p. 99-102. 99
Table 1. Characteristics of some isotopes for medical & biophysical application
Iso-
tope
Half-life
period, days
Basic de-
cay type
Energy of radi-
ation , MeV
Application Required activity
of isotope
32Р 14.36 e- 1.71 β-radiometry of neoformation, up to 300
33Р 25.34 e- 0.248 spermatogenesis, immunoen-
zyme analyze
kBq/kg
57Со 270.9 γ 0.122 calibration of γ-chambers up to102МBq
99mTc 0.25 γ 0.140 isotope scanning 102... 103 MBq
181W 121.2 γ 0.06 enhistotherapy - « -
185W 75.1 e- 0.429 - « - - « -
Table 2. Data of computer analysis for isotope production
Isotope Reaction
Е, МeV
15 20 25
Y1 А, МBq Y1 А, МBq Y1 А, МBq P, kW
32Р 33S(γ,p) 32Р 32Р 1.14 4.37*10-8 19.0 1.41*10-7 61.4 2.19
33Р 34S(γ,p) 33Р 4.55*10-9 1.12 1.60*10-7 39.4 6.44*10-7 15.9 2.19
57Со
58Ni(γ,p) 57Co
58Ni(γ,n) → 57Ni
→ 57Co
1.38*10-6 31.8 3.32*10-5 7.65*102 9.4*10-5 2.16*103 4.98
99Mo 100Mo(γ,n)99Mo 7.92*10-5 1.73*103 4.28*10-4 9.36*104 8.54*10-4 1.87*105 5.18
181W 182W(γ,n) 181W 1.04*10-4 5.36*103 5.03*10-4 2.59*104 8.86*10-4 4.57*104 7.60
185W 186W(γ,n) 185W 4.08*10-5 3.4*103 1.50*10-4 1.24*104 2.48*10-4 2.06*104 7.60
2. ELECTRON LINACS IN RADIOACTIVE
WASTE PROBLEM
2.1. RAW CHARACTERIZATION
Development of nuclear technologies is accompa-
nied by the growth of RAW including long-lived ones.
The waste inside the Chernobyl 4-th unit is of particular
importance because their amount is estimated as much
as 20MCi. Under the circumstances the problem opera-
tive characterization of the waste (i.e. determination of
their amount, activity, radionuclide and element com-
position etc.) is urgent.
This section presents an overview of the RAW char-
acterization methods elaborated in the NSC KIPT and
based on γ-activation analysis using braking radiation of
high-current electron linac.
Taking into account that a RAW sample activated by
high-energy braking photons emits a radiation that is
caused both by its inherent activity and one initiated as a
result of photonuclear reactions, thus an analysis of such
radiation gives quantitative information about radionuc-
lide and element composition of the specimen without
its dissection.
For the analysis of large amount of the RAW samples
by means of γ-activation method and implementation of
other concomitant programs it is needed an electron ac-
celerator with the beam power up to 10 kW and a wide
range of particle energy regulation. The complex LU-20
designed in “Accelerator” R&D Prod. Est. of NSC
KIPT satisfies these requirements [5]. The necessary set
of devices for formation & diagnostics of radiation un-
der γ-activation analysis has been developed.
A studied RAW sample is irradiated as a rule togeth-
er with a specimen of the standard isotope content. Con-
centration of this isotope in the sample is determined by
means of comparison of induced γ-activity of each
sample along the lines corresponding to given isotope
(taking into account their mass).
So, there were investigated the samples of lava-like
fuel-containing mass (LFCM), which was formed in un-
derreactor premises of the wrecked 4-th Unit of
Chernobyl station. The obtained spectrums include the
lines of 237U which was generated under activation pro-
cess in 238U(γ,n)237U reaction. This example demon-
strates the ability of the γ-activation method to analyse
the elements which identification is impossible by
means of traditional spectrometry methods. Thus ob-
tained quantitative data concerning the element content
in the samples of RAW allows carrying out a correlation
analysis as well.
It was demonstrated also the ability of γ-activation
method in analysis of the samples having their own
activity of different nature. So, apart the lines of γ-radi-
ating nuclides (154Eu, 137Cs and 134Cs) there were ob-
served the lines of 89Sr. The last result is especially im-
portant because γ-radiating nuclide 89Sr is created as a
consequence of the β-radiating 90Sr transmutation [14].
2.2. RAW DISPOSAL
2.2.1. The next RAW handling stage is immobiliza-
tion and disposal. The materials and geological struc-
tures contacting with the RAW have to keep their pro-
tective properties with respect to radionuclide displace-
ment under absorbed dose up to 108 Gy during 1000
years and more. The conducted investigations showed a
possibility of application of the electron accelerators
braking radiation in energy range 10...30 MeV to solve
a number of tasks for prognostication of the material
durability under effect of RAW radiation. So, the main
goal of imitation exposure of the materials that are used
for immobilization of radionuclides is a creation of ab-
sorbed doze up to 108 Gy in investigated samples during
100
acceptable period (as a rule no more than 1 year) at con-
trolable parameters of irradiation.
The gamma-ray unit with radionuclide sources (ba-
sically, 60Co) is a traditional radiation source for testing
in doze range up to 108 Gy. The advantage of such tests
is stability of influence conditions to the sample. There-
with, the setup with activity up to 1 MCi is needed to
reach the absorbed doze rate (ADR) about 10 Gy/s.
Electron accelerator can provide the same parameters
under converting its beam to braking photons. So, the
ADR in a sample about 10 Gy/s for electrons with en-
ergy 10 MeV is reached by converting a beam with
power 10 kW, that corresponds to parameters of modern
industrial accelerators (e.g. [5]). A possibility of the
electron energy and flux control provides also an expan-
sion of range of the influence parameters to the sample
under its test.
2.2.2. It is known also that during lasting disposal of
the high-level RAW or nuclear spent fuel can arise a
situation when the RAW immobilization matrix (includ-
ing geological structure) will contact with ground water.
Thus originates a structure of “RAW-water-geological
barrier” type. A radionuclide transport in such structure
determines a reliability of the RAW disposal. Such
transport depends besides all on absorbed dose of radi-
ation from the RAW.
For a research of radionuclide transport processes
the granite specimens (which is considered as a per-
spective environment for disposal of long-lived RAW)
were choosed. A piece of granite was cut into the speci-
mens in the form of blocks with the size of 10x10 mm
in cross-section and 30 mm in thickness. Each block
was covered with epoxy except for 10x10 surface.
Isotope Yb-169 was used as γ-radiating nuclide-
tracer, which is analogous to actinides in its chemical
properties. For this nuclide production under reaction
168Yb(n, γ)169Yb the pellets of stable 168Yb2O3 were irra-
diated by photoneutrons. Then the pellet was dissolved
in concentrated HCl acid (0.2 ml) and finally the
aqueous solution with pH=1.8 was prepared.
Obtained solution (40 ml) together with specimen ir-
radiated up to given dose (3⋅106...3⋅107 Gy) was placed
into thermostable flask. The latter was being heated by
water steam during 32 hours.
Then each specimen was being washed in distillate
water during 24 hours and dried out at 60°C in the dry-
ing box. Further the layers (2...50 µm) from free surface
of the specimen were removed by means of precision
grinding. Material of the removed layers was used for γ-
spectrometry with the Ge(Li)-detector. These results al-
lowed determining a dose dependence of the radionuc-
lide diffusion as well as to find out its mechanism [15].
2.2.3. For the study of radiation & chemical durabil-
ity of granite its samples were irradiated with braking
radiation at two stages: first – at the value of upper
boundary of the braking photons energetic spectrum Eγ
max=10 MeV up to the absorbed dose (AD) of 1,7⋅
107 Gy, after that the samples were activated at Eγ
max=23 MeV during 7 days up to the total AD of 3,0⋅
107 Gy. Then the samples were kept for some days to
reduce their induced radioactivity, ground up into gran-
ules with the size less than 0.83 mm which allowed to
increase their surface area from 6,2 to 59 cm2 and un-
derwent dynamic test on leaching in the plant based on
Soxhlet extractor. Analysis of the leachant γ-spectrums
showed that sodium, rubidium and calcium are leached
from granite most intensely. There was no noticeable re-
lease of uranium and yttrium from these samples [16].
3. OTHER APPLICATIONS AND METRO-
LOGICAL MAINTENANCE
The characteristic γ-radiation of the samples irradiat-
ed by high-energy braking photons can be used also for
operative determination of their element (isotope) com-
position. So, we have showed a possibility of its appli-
cation in the analysis of the rare and noble metals [17-
19] as well as in biophysics [20].
The radiation facilities of the NSC KIPT [5] are en-
able the testing of different materials, devices and con-
struction elements within a wide range of the radiation
parameters and dose values. So, during last period there
was tested a number of the fission reactor elements and
materials [21,22], magnetics [23], as well as semicon-
ductor detectors of γ-radiation [24].
The analytical methods and technologies using brak-
ing photons irradiation [25] demand continuous moni-
toring of the radiation parameters. To provide a certifi-
cation of the accelerators and technologies as well as a
metrological maintenance of the radiation treatment a
number of the working standards and technological
measurement channels were developed [26, 27]. The
latters are based on the sensors that non-disturb a radia-
tion field (Rogovski coils of different modification [28],
radiation – acoustic line [29], thin-wall ionization cham-
bers [30] etc.). Most of them were previously investigat-
ed by means of computer analysis using GEANT code
[31].
The basic results reviewed in the paper were ob-
tained under realization of STCU projects №№ 432,
1580 and 2185.
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103
Table 1. Characteristics of some isotopes for medical & biophysical application
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| id | nasplib_isofts_kiev_ua-123456789-110708 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-07T18:27:07Z |
| publishDate | 2003 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Dikiy, N.P. Dovbnya, A.N. Uvarov, V.L. 2017-01-06T08:36:05Z 2017-01-06T08:36:05Z 2003 Development of new trends in applied nuclear physics with the use of high-energy braking radiation / N.P. Dikiy, A.N. Dovbnya, V.L. Uvarov // Вопросы атомной науки и техники. — 2003. — № 2. — С. 99-102. — Бібліогр.: 31 назв. — англ. 1562-6016 PACS: 84.40.Cb. 81.70.-q. 87.58.Ji https://nasplib.isofts.kiev.ua/handle/123456789/110708 A review is given about investigation in nuclear medicine, atomic energetics (Chernobyl problem including), geology etc. that carried out in the NSC KIPT mainly during last decade on the basis of home made electron linacs. Дано огляд досліджень в області ядерної медицини, атомної енергетики (включаючи проблему Чорнобиля), геології і т.д., що проводилися в ННЦ ХФТІ головним чином протягом останніх 10 років на основі лінійних прискорювачів електронів власного виробництва. Дан обзор исследований в области ядерной медицины, атомной энергетики (включая проблему Чернобыля), геологии и т.д., проводившихся в ННЦ ХФТИ главным образом в течение последних 10 лет на основе линейных ускорителей электронов собственного производства. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Application of the nuclear methods Development of new trends in applied nuclear physics with the use of high-energy braking radiation Розвиток нових напрямків у прикладній ядерній фізиці з використанням високоенергійного гальмівного випромінювання Развитие новых направлений в прикладной ядерной физике с использованием высокоэнергетичного тормозного излучения Article published earlier |
| spellingShingle | Development of new trends in applied nuclear physics with the use of high-energy braking radiation Dikiy, N.P. Dovbnya, A.N. Uvarov, V.L. Application of the nuclear methods |
| title | Development of new trends in applied nuclear physics with the use of high-energy braking radiation |
| title_alt | Розвиток нових напрямків у прикладній ядерній фізиці з використанням високоенергійного гальмівного випромінювання Развитие новых направлений в прикладной ядерной физике с использованием высокоэнергетичного тормозного излучения |
| title_full | Development of new trends in applied nuclear physics with the use of high-energy braking radiation |
| title_fullStr | Development of new trends in applied nuclear physics with the use of high-energy braking radiation |
| title_full_unstemmed | Development of new trends in applied nuclear physics with the use of high-energy braking radiation |
| title_short | Development of new trends in applied nuclear physics with the use of high-energy braking radiation |
| title_sort | development of new trends in applied nuclear physics with the use of high-energy braking radiation |
| topic | Application of the nuclear methods |
| topic_facet | Application of the nuclear methods |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/110708 |
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