Production of medical isotopes at electron accelerators
A brief summary of the production medical isotopes by powerful linac electron accelerator is presented.
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| Zitieren: | Production of medical isotopes at electron accelerators / N.P. Dikiy, A.N. Dovbnya, Yu.V. Lyashko, E.P. Medvedeva, Yu.D. Tur, V.L. Uvarov, I.D. Fedorets, S.A. Pashchuk, I.G. Evseev // Вопросы атомной науки и техники. — 2000. — № 2. — С .58-61. — Бібліогр.: 19 назв. — англ. |
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Dikiy, N.P. Dovbnya, A.N. Lyashko, Yu.V. Medvedeva, E.P. Tur, Yu.D. Uvarov, V.L. Fedorets, I.D. Pashchuk, S.A. Evseev, I.G. 2015-05-27T12:41:34Z 2015-05-27T12:41:34Z 2000 Production of medical isotopes at electron accelerators / N.P. Dikiy, A.N. Dovbnya, Yu.V. Lyashko, E.P. Medvedeva, Yu.D. Tur, V.L. Uvarov, I.D. Fedorets, S.A. Pashchuk, I.G. Evseev // Вопросы атомной науки и техники. — 2000. — № 2. — С .58-61. — Бібліогр.: 19 назв. — англ. 1562-6016 PACS: 87.58.Ji https://nasplib.isofts.kiev.ua/handle/123456789/82274 A brief summary of the production medical isotopes by powerful linac electron accelerator is presented. The work was fulfilled according to the treaty of cooperation between NSC KIPT and CEFET-PR: “Acordo de cooperacao entre o Instituto de Fisica e Tecnologia de Kharkov (Ucraina) e o Centro Federal de Educacao Tecnologica do Parana de Curitiba (CEFET-PR)” from October 21, 1998. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Аpplication of the nuclear methods Production of medical isotopes at electron accelerators Получение медицинских изотопов при помощи ускорителей электронов Article published earlier |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine |
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DSpace DC |
| title |
Production of medical isotopes at electron accelerators |
| spellingShingle |
Production of medical isotopes at electron accelerators Dikiy, N.P. Dovbnya, A.N. Lyashko, Yu.V. Medvedeva, E.P. Tur, Yu.D. Uvarov, V.L. Fedorets, I.D. Pashchuk, S.A. Evseev, I.G. Аpplication of the nuclear methods |
| title_short |
Production of medical isotopes at electron accelerators |
| title_full |
Production of medical isotopes at electron accelerators |
| title_fullStr |
Production of medical isotopes at electron accelerators |
| title_full_unstemmed |
Production of medical isotopes at electron accelerators |
| title_sort |
production of medical isotopes at electron accelerators |
| author |
Dikiy, N.P. Dovbnya, A.N. Lyashko, Yu.V. Medvedeva, E.P. Tur, Yu.D. Uvarov, V.L. Fedorets, I.D. Pashchuk, S.A. Evseev, I.G. |
| author_facet |
Dikiy, N.P. Dovbnya, A.N. Lyashko, Yu.V. Medvedeva, E.P. Tur, Yu.D. Uvarov, V.L. Fedorets, I.D. Pashchuk, S.A. Evseev, I.G. |
| topic |
Аpplication of the nuclear methods |
| topic_facet |
Аpplication of the nuclear methods |
| publishDate |
2000 |
| language |
English |
| container_title |
Вопросы атомной науки и техники |
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| format |
Article |
| title_alt |
Получение медицинских изотопов при помощи ускорителей электронов |
| description |
A brief summary of the production medical isotopes by powerful linac electron accelerator is presented.
|
| issn |
1562-6016 |
| url |
https://nasplib.isofts.kiev.ua/handle/123456789/82274 |
| citation_txt |
Production of medical isotopes at electron accelerators / N.P. Dikiy, A.N. Dovbnya, Yu.V. Lyashko, E.P. Medvedeva, Yu.D. Tur, V.L. Uvarov, I.D. Fedorets, S.A. Pashchuk, I.G. Evseev // Вопросы атомной науки и техники. — 2000. — № 2. — С .58-61. — Бібліогр.: 19 назв. — англ. |
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PRODUCTION OF MEDICAL ISOTOPES AT ELECTRON ACCELERA-
TORS
N.P. Dikiy, A.N. Dovbnya, Yu.V. Lyashko, E.P. Medvedeva, Yu.D. Tur, V.L. Uvarov
National Science Center “Kharkov Institute of Physics and Technology”, Kharkov, Ukraine
I.D. Fedorets
Kharkov National University, Kharkov, Ukraine
S.A. Pashchuk, I.G. Evseev
Centro Federal de Educacao Tecnologica do Parana de Curitiba (CEFET-PR), Brazil
A brief summary of the production medical isotopes by powerful linac electron accelerator is presented.
PACS: 87.58.Ji
The majority of medical isotopes are produced on
high-power reactors and cyclotrons. The problems of a
radiation waste and negative public opinion resulted in
decrease of reactor quantity in the world [1,2]. Despite
of wide opportunities of reactors and cyclotrons the
deficit of some isotopes is observed. For example it is
89Sr, 188Re, 103Pd. The isotopes, which were applied ear-
lier, are extensively used again. The radiobioconjugates
are investigated for injection of isotopes in cancer cells
[3].
This paper is purposed to the medical isotope pro-
duction with the use of bremsstrahlung, photoneutrons
at a high-power electron accelerator of NSC KIPT. The
radiochemical or physical separation isotopes are used
if it is necessary. In the last few years at R&D "Acceler-
ator" the activity on upgrading the linear electron accel-
erator [4] is conducted. Now the accelerator operates at
the energy 25-27 MeV and current up to 1 mA. These
parameters of the accelerator have been used to estimate
the yield of isotopes considered below.
For the last two years the technology of the 99mTc iso-
tope most widespread in the medical practice was devel-
oped [5]. The accelerator is capable to produce up to 4
Ci of a parent 99Mo isotope in one day. For production
of this isotope the nuclear reactions [6,7] can be used:
100Mo(γ, n) 99Mo (T1/2 = 66.02 hrs),
98Mo(n,γ) 99Mo (T1/2 = 66.02 hrs).
The distinctive feature of such a method is the use of
molybdenum with natural isotope composition (the
abundance of 100Mo is 9.63 %, 98Mo - 24.13 %) and two
channels of production 99Mo. To use this isotope the
technology of electrolytic deposition of 99mTc on a car-
bon substrate with subsequent dissolving 99mTc to tech-
netium acid solution was developed. Now the works on
development of a new technology of 99mTc mass produc-
tion and distribution of this isotope for the use in medi-
cal establishments of the East region of Ukraine are
conducted.
Taking into account the world tendencies, the physi-
cal principles of producing radioisotopes are developed.
43K (T1/2 = 22.3 hrs) being used in cardiology can be ef-
fectively generated at the linac. The most intensive
gamma radiation 43K has the energy 372 keV. One can
use the reaction [8]:
44Ca(γ,p)43K (Q = −12.3 MeV).
The reaction cross section on the gamma radiation
withE= 20 MeV practically is compared with the (γ,n) -
reaction. It allows one even for abundance of the 44Ca
2.08 % isotope to produce in one day about 10 GBk of
this isotope and to realise diagnostics of cardiac dis-
eases for 100 patients. As compared with 201Tl (T1/2 =
73.1 hrs) this isotope has radiation loading on the pa-
tient organism approximately three times smaller [9].
The reaction 42Ca(n,p)42K (T1/2 =12.5 hrs) has a cross
section on nuclear fission neutrons equal to 2.6 mb and
its contribution to the activity of kalium will be insignif-
icant [10].
Production of isotope for cardiology and positron
emission tomography (PET) simultaneously is possible
with the use of nuclear reactions:
84Sr(γ,2n) 82Sr, (Q = –20.76 MeV).
82Sr has the half-life period of 25.0 day’s [11] and is de-
caying to 82Sr, which has the half-life period of 1.25
minutes. The basic characteristic of this generator is the
small radiation loading on the patient. The abundance of
82Sr isotope is only 0.54 % therefore the expected yield
of 82Sr on strontium of a natural isotope composition
will be 0.1 GBk per day. But even this will allow fulfill
up to 1000 analyses. Therefore there is cost effective-
ness of 82Sr production. It also can be used in cardiac
therapy. The nuclear reaction depressing the quality of
this generator is:
84Sr(γ,n) 83Sr, (T1/2 = 32.4 hrs).
83Sr decays to 83Rb (T1/2 = 86,2 day). Therefore after the
complete decay of 83Sr (about 6 days) from the irradiat-
ed target 83Rb will be released and further the generator
will be ready to use 82Rb.
Significantly best production conditions are realized
by manufacturing the generator of 68Ga. For this pur-
pose the following nuclear reaction can be used:
70Ge(γ,2n)68Ge, (T1/2 = 287 days, Q = –20 MeV)
→ 68Ga, (T1/2 = 68 min.)
The abundance of 70Ge is 20.5 %; therefore the yield of
68Ge isotope is about 0.3 GBk per day [11]. 68Ga has a
low value of half-life period therefore the activity ob-
tained for one day will allow fulfilling up to 4000 analy-
ses and its cost effectiveness is high. 68Ga can be used
for diagnostics of malignant tissues that allows one to
maintain a high frequency of its application.
A promising generator 42K can be obtained by nucle-
ar reactions:
58 ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 2000, № 2.
Серия: Ядерно-физические исследования (36), c. 58-61.
.
46Ca(γ,α)42Ar, (T1/2 = 32.9 years, Q = −11.1 MeV)
→ 42K (T1/2 = 12.36 hrs).
The abundance of 46Ca is only 0.004 % and, conse-
quently, the production of a natural isotope composition
on calcium is meaningless. The use of enriched 46Ca iso-
tope allows producing with a rather high efficiency, i.e.
6 MBk of 42Ar per day.
The production of 111Sn can be realized by nuclear
reactions:
112Sn(γ,n)111Sn (+111mSn), (T1/2 = 35.3 min (7,7 min)
Q = −10.8 MeV)→ 111In (T1/2 = 2.8 days).
Simultaneously on tin of a natural isotope composition
the generator 113In is implemented by nuclear reactions:
114Sn(γ,n)113Sn, (T1/2= 115,2 days) Q= −10,3 MeV)
→ 113mIn (T1/2 = 99,4 min).
The abundance of 112Sn, 114Sn is 0.95, 0.65 %, respec-
tively, and productivity on tin of a natural isotope com-
position will be 15 GBk for 111In and 0.3 GBk for parent
isotope 113mSn per day.
Production of 45Ca (pure emitter of β-particles) for
treatment of bones cancer is possible with the use of nu-
clear reactions [11]:
45Sc(n,p)45Ca, (T1/2 = 163.8 days, Q = +0.53 MeV).
It is well known that the linac can be a neutron
source [13-15]. The neutron intensity for the energy 30
MeV is approximately 1012 per kW of the electron beam
power. In our case it is possible to achieve the activity
of 45Ca 0.3 GBk per day. It is enough for treatment of
10 patients, and the cost of one dose is 3-5 times less
than for treatment by 89Sr drugs. Note, that at the accel-
erator one can produce also 89Sr using the nuclear reac-
tions [11] :
89Y(n,p)89Sr, (T1/2 = 50.5 days, Q = −0.72 MeV),
92Zr(n,α)89Sr, (T1/2 = 50.5 days, Q = +3.39 MeV),
but, in this case, the cost of manufacturing the activity
unity will be approximately 10 times more, than for 45Ca
(the abundance of 89Y and 92Zr is 100 and 17.11 %, re-
spectively).
In this sense the production of the 87mSr generator for
diagnostics of cancer deserves attention. There one can
use the nuclear reactions [11]:
89Y(γ,2n)87Y, (T1/2 = 80.3 hrs, Q = −20.8 MeV)
→ 87mSr (T1/2 = 2.8 hrs).
The estimation of 87Y yield for 30 MeV electrons makes
30 GBk per day. It enables significant reducing the cost
price of the analysis for diagnostics of bones cancer, a
well as the radiation loading onto the patient in compar-
ison with the use of 85Sr hundreds times as large.
At the linac the production of 123,125I is possible by the
reactions:
126Xe(γ,n)125Xe, (T1/2 = 17 hrs, Q = −10.12 MeV)
→ 125I (T1/2 = 59.9 days)
124Xe(γ,n)123Xe, (T1/2 = 2,08 hrs, Q = −10.2 MeV)
→ 123I (T1/2 = 13.3 hrs).
The abundance of 124Xe, 126Xe isotopes is 0.096 and
0.09 %, respectively. The estimation of 123I, 125I produc-
tivity gives 0.1 and 12 GBk per day, respectively. But
123I has considerably best parameters for diagnostics of
the thyroid gland (reducing the radiation loading, best
conditions for radiation detecting). The 125I has a wide
application for scientific (for example, for studying the
activity of Auger electrons on the cancer cell) and ra-
dioimmune examinations. Therefore, their production in
Ukraine shows an impressive promise.
The great opportunities of the linac can be also im-
plemented by manufacturing isotopes for brachytherapy.
In this case the samples with a high specific activity are
necessary. The original methods of making γ-radiation
of high intensity in small volumes, developed at R&D
"Accelerator", allow to gain 103Pd, 181W with 1.5 mCi
specific activity for samples of 6 mg in weight. For this
purpose the following nuclear reactions [11] can be
used:
104Pd(γ,n)103Pd, (T1/2 = 16.9 days, Q = −10.0 MeV)
182W(γ,n)181W, (T1/2 = 121.2 days, Q = −8.1 MeV).
The abundance of 104Pd, 182W is 11.4 % and 26,3 %, re-
spectively. 103Pd is promising for brachytherapy of
prostate cancer, and 181W for brachytherapy of a wide
application (radiation source, small-sized devices for
determination of element composition in geology, agri-
culture, engineering on the base of CdTe(Zn) crystals).
For this purpose 180mTa is suitable produced by the reac-
tion:
181Ta(γ,n)180mTa, (T1/2 = 8,1 hrs, Q = −8.5 MeV).
The abundance of 181Ta is 99,99%.
For brachytherapy one can use also 91mNb produced
by the nuclear reaction:
92Mo(γ,n)91Mo, (T1/2 = 15.5 min, Q = –12.7 MeV)
→ 91mNb, (T1/2 = 62 days).
The basic radiation loading of 91mNb is performed at the
expense X-rays and Auger electrons (radiation level for
1204.5 and 104 MeV is 3 and 0.5 %, respectively).
91mNb also can be used for treatment of lymph tumour
[16]. The expected productivity of 91mNb on molybde-
num of a natural isotope composition will make
0.7 GBk per day.
The methods of concentrating the gamma radiation
allow to producing model isotope sources for calibra-
tion of gamma chambers and defectoscopy of 57,58Co
with a cost effectiveness at a level of foreign firms. For
this one can use nuclear reactions:
58Ni(γ,n)57Ni, (T1/2 = 36.8 days, Q = −12.2 MeV)
→ 57Co (T1/2 = 290.7 days).
59Co(γ,n)58Co, (T1/2= 70.78 days, Q=−10.5 MeV).
58Co is used for studying the lifetime of positrons in
condensed medium also. This method is effectively ap-
plied to the study of radiation defects in materials of nu-
clear power engineering. 58Co for medicine application
can be produced by the nuclear reactions:
58Ni(n,p)58Co, (T1/2= 70.78 days, Q=+0.39 MeV).
The abundance of 58Ni is 67.8 % and the expected yield
of 58Co will make 2.4 GBk per day (cross-section for 6
MeV neutrons is 650 mb). Moreover, on the γ-radiation
beam the production of 57Co and on the photoneutron
beam the production of 58Co will be realized simultane-
ously.
Promising is the production of the 188W generator at
the linac. For this purpose the following nuclear reac-
tions can be used:
192Os(γ,α)188W, (T1/2 = 69.4 days, Q=+0.36 MeV)
→ 188Re, (T1/2 = 16.98 hrs).
59
The abundance of 192Os is 41%. The activity, which
is achieved in this case, will be 50 MBk per day. It al-
lows conducting diagnostics for ∼200 patients and the
cost price of one analysis is little higher than that in the
case of other isotopes. But potentialities of this isotope
for diagnostics are much wider, than traditional.
The production of 186Re isotope merits attention too.
For this one can use the reaction:
187Re(γ,n)186Re, (T1/2 = 90.6 hrs, Q=−7.37 MeV).
It is possible to produce up to 3200 GBk 186Re per
day. But its use for diagnostics or treatment is limited
by risk of accumulating its activity with taking into ac-
count the inactive isotope (activity of 1 mg rhenium of a
natural isotope composition is 150 GBk of 186Re). 186Re
can be used for treatment (β-particle with a maximal en-
ergy of 1.07 MeV) as well as for diagnostics. The inap-
preciable activity of 184Re also will be present, but with-
out β-activity, that is important for the use of 186Re for
treatment. Production of isotopes of rhenium does not
pollute environment as against use 99mTc (99Tc (T1/2 =
2.13.105 years) [17,18].
The production of 186Re is possible by reaction
187Os(γ,p)186Re, (T1/2= 90,6 hrs, Q =−6,587 MeV)
also. The Ukrainian molybdenum ore contain of trace
element Re which decay on 187Os. Therefore the produc-
tion molybdenum is accompanied by extraction of 187Os.
The cross section is nearly 1 mb. Therefore per day it is
possible to produce 2 GBk 186Re.
The production of isotopes at the linac can compete
also in the traditional field of use of reactors and cy-
clotrons. For example, the production of 32P with the use
of the nuclear reaction:
32S(n,p)32P, (T1/2 = 14.36 days, Q = +0.96 MeV)
allows producing about 12 GBk of 32P per day. Simulta-
neously on sulphur of natural isotope composition the
nuclear reactions:
34S(γ,p)33P, (T1/2 = 25.34 days, Q=−10.88 MeV),
33S(γ,p)32P, (T1/2 = 14.36 days, Q=−9.57 MeV)
will be realized but with significantly lower yield, than
in (n,p) - reaction. The abundance of sulphur isotopes is
95, 0,75, 4,2 % for 32S, 33S, 34S, respectively.
Also by means of the (n,p)–reaction 64Cu can be pro-
duced for using in the positron emission tomography:
64Zn(n,p)64Cu, (T1/2 = 12,7 years, Q = +0,21 MeV).
The abundance of 64Zn is 48,6 % and the expected pro-
ductivity of 64Cu will make 70 GBk per day (cross sec-
tion for neutrons of nuclear fission is 30 mb).
Production of isotopes 11C, 13N, 15O, 18F for the positron
emission tomography is possible at high-power electron
accelerator also. In our opinion attention should be giv-
en to the nuclear reactions [11,15]:
20Ne(γ,np)18F, (T1/2 = 109.8 min, Q= –23.27 MeV),
20Ne(γ,2n)18Ne, (T1/2 = 1,6 s , Q = –28.5 MeV)
→ 18F (T1/2 = 109.8 min).
The estimation of the 18F yield for 30 MeV gives 10
GBk per hour that allows to conducting diagnostics on
ten positron-emission tomographs simultaneously.
Parameters of isotopes produced at electron linear accelerator.
N Isotope T1/2 Energy, keV (intensity, %) Possible use
β-particle γ-radiation
1 18F 109.8 min 649(97) 511(193) PET
2 32P 14.3 days 1709(100) Osteotherapy
3 33P 25 days 248(100) Osteotherapy
4 42K 12.4 hrs 3520(82) 1524,7(18) Myocardial therapy
5 43K 22.6 hrs 830( 83) 372/ 617(90/72) Myocardial therapy
6 45Ca 164 days 257(100) Bone-pain therapy
7 57Co 267 days 122(85) Calibration γ-chamber
8 58Co 70.8 days 474(15) 811/ 511(81/30) Defectoscopy
9 58mCo 9.15 hrs Auger electron Radiobioconjugate
10 64Cu 12.7 hrs 573(38) 511(37) PET
11 68Ga 68 min 1940(96) 511(178) PET
12 73As 80.3 days Auger electron Radiobioconjugate
13 82Rb 1.25 min 3500(100) 511(189) Myocardial therapy
14 87mSr 2.8 hrs 388(84) Osteotherapy, diagnostics
15 89Sr 50.5 days 1463(100) Bone-pain therapy
16 62 days KX17(46); 1204,5(3) Radiobioconjugate
17 6.02 hrs 140,5(89,6) Universal
18 103mRh 56.1 min Auger electron Radiobioconjugate
19 103Pd 16.9 days KX20,5(77) Brachytherapy
20 111In 2.8 days 171(91)/245(94) Universal
21 113mIn 99.4 min 392(64) Universal
22 119Sb 38 hrs Auger electron Radiobioconjugate
23 123I 13.3 hrs 159(83) Radiobioconjugate
24 125I 59.9 days KX28(139) Radioimmunotherapy
25 180mTa 8.1 hrs KX57(73) Brachytherapy
26 181W 121 days KX59(65) Brachytherapy
27 186Re 90.6 hrs 1080(92) 137(9,2) Osteotherapy, universal
28 188Re 16.9 hrs 2135(78) 155(15) Osteotherapy, universal
29 195mPt 4.02 days Auger electron 99(11) Radiobioconjugate
60
In particular, it is necessary to note the possibility of
isotope production for intranuclear irradiation of cancer
cells with Auger electrons: 58mCo, 73As, 103mRh, 119Sb,
195mPt. It is well known that efficiency of Auger electron
action in the nucleus of a cell is hundreds times higher
than that for irradiation with electrons or gamma quanta
of a high energy. To use these isotopes the carriers are
developed. The carriers will allow transporting isotopes
in the nucleus of a cell [3]. The high yield of 58mCo (5,6
GBk per hour) is achieved by the nuclear reactions:
58Ni(n,p)58mCo, (T1/2 = 9.15 hrs, Q=+0.39 MeV).
The considerable yield of isotopes is achieved by means
of the following nuclear reactions:
120Te(γ,n)119Te, (T1/2 = 4.7 days, Q= −10.29 MeV)
→ 119Sb (T1/2 = 38.1 hrs);
104Pd(γ,n)103Pd, (T1/2 = 16.9 days, Q= −10.0 MeV)
→ 103mRh (T1/2 = 56.1 min);
74Se(γ,n)73Se, (T1/2 = 7.15 hrs, Q= −12.08 MeV)
→ 73As (T1/2 = 80.3 days).
Production of 73As is very important for treatment of
metastases in bones. Bone-pain palliation therapy may
be indicated in about 50000 cancer patients in Ukraine
alone. Unlike other isotopes, which can be used for this
purpose, 73As does not damage the marrow. 73As can be
used also for brachytherapy. Its properties in particular
are exhibited for treatment of tumours of a small size.
The layer of half weakening of radiation for 73As is 1,3
mm, that allows to use it for brachytherapy of tumours
by the size down to 3-5 mm.
Last years the platinum complex compound attracted
increased attention of oncologists [19]. The classical
representative of this group (cisplatin) has widely come
into the practice of malignant neoformation treatment. It
is known that cisplatin and the similar preparations are
being incorporated into a nucleus of the cancerous cell
during chemotherapy, inhibit the embedding of the pre-
decessors into macromolecule DNA and RNA. It is pro-
posed for cancerous cell destruction to use the high lin-
ear energy transfer (LET) effect of electrons that ap-
peared decays of isotopes. The radioactive isotope
195mPt produced by using bremsstrahlung:
195Pt(γ,γ′)195mPt, (T1/2 = 4 days, Q = −0.259 MeV);
196Pt(γ,n)195mPt, (T1/2 = 4 days, Q = −8.18 MeV);
199Hg(γ,α)195mPt, (T1/2 = 4 days, Q = 0.561 MeV);
196Pt(γ,p)195mIr→195mPt, (T1/2=4 days, Q=−8.37 MeV);
197Au(γ,np)195mPt, (T1/2 = 4 days, Q = −13.977 MeV).
The yield of 195mPt is low but advantage is high. The
abundance ratio of isotopes 195,196Pt, 199Hg, 197Au are
33.8, 25.2, 16.8, 100%, respectively. The cross section
is smaller 0.1 mb for these nuclear reactions. Therefore
per day it is possible to produce 0.5 GBk of 195mPt.
So, the high-power electron accelerator of NSC
KIPT is capable to produce practically all of isotopes
for nuclear medicine without environmental pollution
and with high cost efectiveness. In particular the advan-
tage can be realized for complex production of many
isotopes.
The work was fulfilled according to the treaty of coopera-
tion between NSC KIPT and CEFET-PR: “Acordo de coope-
racao entre o Instituto de Fisica e Tecnologia de Kharkov
(Ucraina) e o Centro Federal de Educacao Tecnologica do
Parana de Curitiba (CEFET-PR)” from October 21, 1998.
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N.P. Dikiy, A.N. Dovbnya, Yu.V. Lyashko, E.P. Medvedeva, Yu.D. Tur, V.L. Uvarov
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