Optimization of conditions for ⁶⁷Cu photonuclear production
Radiopharmaceuticals based on the ⁶⁷Cu isotope have found wide use in immunotherapy. The present paper analyzes the conditions of ⁶⁷Cu production by the ⁶⁸Zn(γ,p) ⁶⁷Cu reaction at an electron accelerator in relation to the target isotope and hot impurities yield, as well as the radiation risks. Cons...
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| Zitieren: | Optimization of conditions for ⁶⁷Cu photonuclear production / A.N. Dovbnya, M.A. Dolzhek, G.D. Pugachev, O.A. Repikhov, A.V. Torgovkin, V.L. Uvarov, V.S. Shestakova, B.I. Shramenko // Вопросы атомной науки и техники. — 2015. — № 6. — С. 160-164. — Бібліогр.: 7 назв. — англ. |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1859825778612502528 |
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| author | Dovbnya, A.N. Dolzhek, M.A. Pugachev, G.D. Repikhov, O.A. Torgovkin, A.V. Uvarov, V.L. Shestakova, V.S. Shramenko, B.I. |
| author_facet | Dovbnya, A.N. Dolzhek, M.A. Pugachev, G.D. Repikhov, O.A. Torgovkin, A.V. Uvarov, V.L. Shestakova, V.S. Shramenko, B.I. |
| citation_txt | Optimization of conditions for ⁶⁷Cu photonuclear production / A.N. Dovbnya, M.A. Dolzhek, G.D. Pugachev, O.A. Repikhov, A.V. Torgovkin, V.L. Uvarov, V.S. Shestakova, B.I. Shramenko // Вопросы атомной науки и техники. — 2015. — № 6. — С. 160-164. — Бібліогр.: 7 назв. — англ. |
| collection | DSpace DC |
| container_title | Вопросы атомной науки и техники |
| description | Radiopharmaceuticals based on the ⁶⁷Cu isotope have found wide use in immunotherapy. The present paper analyzes the conditions of ⁶⁷Cu production by the ⁶⁸Zn(γ,p) ⁶⁷Cu reaction at an electron accelerator in relation to the target isotope and hot impurities yield, as well as the radiation risks. Consideration has been given to some variants of the technological target 40 g in weight made from natural zinc, and one enriched up to 99% in the ⁶⁸Zn isotope. The target exposition to bremsstrahlung with end-point energy 30 and 60 MeV was studied. It has been found that the use of enriched target results in reduction of both the radiation risk (down to 10⁻⁴) and the scope of waste han-dling procedures.
Радіофармпрепарати на основі ізотопу ⁶⁷Cu широко використовуються в імунотерапії. У повідомленні проаналізовані умови його виробництва на прискорювачі електронів за реакцією ⁶⁸Zn(γ,n)⁶⁷Cu відносно виходу цільового продукту, а також гарячих домішок і радіаційних ризиків. Розглянуто варіанти технологічної мішені масою 40 г із цинку природного складу і збагаченого до 99% за ізотопом ⁶⁸Zn, активованою гальмівним випромінюванням із граничною енергією 30 і 60 МеВ. Показано, що при використанні збагаченої мішені радіаційний ризик знижується до 10⁻⁴, а також значно зменшується обсяг процедур з відходами.
Радиофармпрепараты на основе изотопа ⁶⁷Cu широко используются в иммунотерапии. В сообщении проанализированы условия его производства на ускорителе электронов по реакции ⁶⁸Zn(γ,n)⁶⁷Cu в отношении выхода целевого продукта, а также горячих примесей и радиационных рисков. Рассмотрены варианты технологической мишени массой 40 г из цинка природного состава и обогащенного до 99% по изотопу ⁶⁸Zn, активированной тормозным излучением с граничной энергией 30 и 60 МэВ. Показано, что при использовании обогащенной мишени радиационный риск снижается до 10⁻⁴, а также значительно уменьшается объем процедур с отходами.
|
| first_indexed | 2025-12-07T15:28:42Z |
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ISSN 1562-6016. ВАНТ. 2015. №6(100) 160
OPTIMIZATION OF CONDITIONS FOR 67Cu PHOTONUCLEAR
PRODUCTION
A.N. Dovbnya, M.A. Dolzhek, G.D. Pugachev, O.A. Repikhov, A.V. Torgovkin, V.L. Uvarov,
V.S. Shestakova, B.I. Shramenko
National Science Center “Kharkov Institute of Physics and Technology”, Kharkov, Ukraine
E-mail: uvarov@kipt.kharkov.ua
Radiopharmaceuticals based on the 67Cu isotope have found wide use in immunotherapy. The present paper ana-
lyzes the conditions of 67Cu production by the 68Zn(γ,p) 67Cu reaction at an electron accelerator in relation to the
target isotope and hot impurities yield, as well as the radiation risks. Consideration has been given to some variants
of the technological target 40 g in weight made from natural zinc, and one enriched up to 99% in the 68Zn isotope.
The target exposition to bremsstrahlung with end-point energy 30 and 60 MeV was studied. It has been found that
the use of enriched target results in reduction of both the radiation risk (down to 10-4) and the scope of waste han-
dling procedures.
PACS: 07.85.-m, 81.40wx, 87.53-j, 87.53Wz
INTRODUCTION
Nowadays, commercial isotope production is mainly
based on the use of nuclear reactors (see, e.g., ref. [1]).
However, the fission of 235U results in the production of
side radioactive products, thereby giving rise to the
problem of long-lived radioactive waste. Besides, the
use of highly enriched 235U is connected with the danger
of its uncontrolled proliferation.
An alternative method of radioisotope production
lies in the use of heavy-particle/electron accelerators.
Thus, 67Cu, as one of the most promising isotopes for
radiotherapy of tumors by monoclonal antibodies, can
be produced in the reactions under the action of neu-
trons, protons, α-particles, and also, high-energy pho-
tons. It has been demonstrated in ref. [2] that the photo-
nuclear technology using the reaction 68Zn(γ,р)67Cu
provides the best conditions for the desired isotope pro-
duction with regard to its total yield and the radionu-
clide-impurity production, even if a target made from
natural zinc is used.
The major sources of isotope production hazards
originate from radiation of the target isotope, hot impu-
rities, and also target device elements. The individual
risk r of stochastic effects occurrence due to personnel
irradiation is given by the relation r=rεD, where D is
the individual absorbed dose, and rε is the total death
risk factor due to radiation, taken to be 5.6·10-2 events
per 1 man·Sv for professional irradiation. By interna-
tional practice, the boundary value of the individual risk
of personnel irradiation is taken to be 10-3 per annum
[3].
The present paper is concerned with the sources and
levels of radiation risks, and also, with the ways of their
reduction under 67Cu producing at an electron accelera-
tor.
1. MAIN REACTIONS
At activation of a zinc target of natural isotopic
composition (64Zn – 48.6%, 66Zn – 27.9%, 67Zn – 4.1%,
68Zn – 18.8%, 70Zn – 0.6%) in the mixed X,n-radiation
field, the yield of 67Cu and hot impurities, which give
the main dose-forming contribution to the target radia-
tion, goes by the reactions:
68Zn (γ,р) 67Cu, 67Zn (n,р) 67Cu,
64Zn (γ,2n) 62Zn, 64Zn (γ,n) 63Zn,
70Zn (γ,n) 69mZn, 68Zn (n,γ) 69mZn,
64Zn (n,р) 64Cu, 66Zn (γ,nр) 64Cu,
66Zn (γ,n) 65Zn, 64Zn (n,γ) 65Zn.
In the subsequent calculations, the maximum 67Cu
activity of the natural zinc target by EOB was put to be
3.7·109 Bq (100 mCi). The concomitant radionuclide
activity data required for estimating the radiation risks
were obtained from the experiments at an 36 MeV elec-
tron accelerator when irradiating the 40g natural zinc
target in the (240 μA; 10 h) run. The data on the 63Zn
yield were obtained by calculations using the following
formula
max
0 max( ) ( , )
th
E
E
N N E f E E dE
γ
γ γ γσ= ∫ , (1)
where N0_is the number of nuclei of the initial isotope,
σ(Еγ) is the reaction cross section as a function of γ-
quantum energy Еγ , Е th is the reaction threshold, Еγmах
is the end-point energy of the bremsstrahlung spectrum,
f (Еγmах, Еγ) is the function describing the X-ray spec-
trum (computed with the use of the GEANT 4 package
[4]).
2. 67Cu PRODUCTION PROCESS AT THE
“ACCELERATOR” Sc&R Est, NSC KIPT
2.1. By the end of target irradiation at an accelerator,
the contribution of short-lived (66Cu, 68Cu, 69Cu,63Zn,
69Zn) and long-lived (65Zn, 69Zn, 62Zn, 63Zn, 64Cu) radio-
nuclides to the overall level of target radiation is hun-
dreds times higher than the 67Cu radiation level. Be-
sides, in the process of decay, the short-lived radionu-
clides emit high-energy gammas, and that necessitates a
substantial increase in the radiation shield thickness.
Therefore, for the decay of short-lived isotopes, the ir-
radiated target must be cooled in the accelerator vault.
The optimum cooling period for natural target is deter-
mined mainly by decay of the 62Zn, 63Zn isotopes, and
makes 3 to 12 hours.
After cooling, the target is delivered by means of a
pneumatic tube from the accelerator vault to a transport
container (TC) situated in a room above the vault. Then,
by using an electric hoist, TC is transferred to an inlet
box of the radiochemical laboratory.
2.2. The layout of the laboratory including the rooms
and locations of the target on its way from TC to a tech-
mailto:uvarov@kipt.kharkov.ua
ISSN 1562-6016. ВАНТ. 2015. №6(100) 161
nological box TB (the points А1, А2, А6, А7,) is shown
in Figure. The irradiated sample from TC is remotely
discharged to a stationary box TB having iron and lead
walls, where all the procedures of the 67Cu extraction are
carried out (point A8).
70
69
Ф ФФ ФА8
А9
А7А6
А2
А10
А1
60
00
Room №16
Room №17
Room №18
Room №15
ТC ТB
Layout of the radiochemical laboratory
with the reference points
The radiation level near the TB surface is deter-
mined by the activity of the target being inside, and al-
so, by a liquid radioactive waste (LRW) tank, located at
the bottom of the box. The tank is filled weekly with
LRW within one to three month period.
2.3. The specified permissible level of the equivalent
dose rate (EDR) at the NSC KIPT makes 8.2 μSv/h. The
expected EDR value was calculated at the following
points of the plant (see Figure):
А1 – the point near the transport container in the
corridor;
А2 – the point in a receiving chamber (room No 18);
А6 – the point near the chamber for transporting the
irradiated sample to the technological box (room No 17;
А7 – the point behind the technological box (room
No 17);
А8 – the work seat before the technological box for
operation with the 67Cu isotope (room No 16);
А9 – the work seat before the 67Cu prepackage de-
vice PD (clean room №16);
А10 – the LRW tank.
3. ANALYSIS OF ISOTOPE CONTRIBUTION
TO EDR
The relationship between the absorbed dose rate
caused by a point gamma source at a distance R, and the
source activity M, expressed in mCi, is determined by
the formula [3]:
D
•
=2.35М·Кγ/R2, μGy/sec = 8.46М·Кγ/R2, mGy/h,
(2)
where Кγ[roent·cm2/(h·mCi)] is the specific gamma-ray
constant, which shows the exposition dose rate pro-
duced by the 1 mCi point γ-source at a distance of 1 cm
for 1 hour. The refined values of the specific γ-ray con-
stants for each radionuclide were calculated with due
regard for its radiation spectrum and the number of
gammas per 1 decay according to a BNL database [5].
The results are given in the Table 1. Since the quality
factor of the 0.1 to 2 MeV gammas is equal to 1, then
the equivalent dose H can be considered equal to the
absorbed dose D.
As it is evident from the Table 2, with consideration
for the decay rate of the 67Cu and impurities, it is desir-
able that the process operations should be performed, as
expected, no sooner than 3 hours after irradiation. Then
the 62Сu, 66Сu, 68Сu and 69Сu isotopes, having the half-
life less than 10 minutes, would not contribute to the
target radiation.
At the 67Cu separation, other copper isotopes will be
presented in the extract also. In particular, 64Сu
(Т1/2=12.7 h) will transform to 64Ni. The concentration
of 64Ni and 62Ni is expected to be comparable with the
67Сu content. In turn, the ratio of the 67Сu and 63Сu nu-
clei in the extract was calculated by formula (1) ac-
counting the percentage of the initial nuclei. The ratio
was found to be 0.042 and 0.062 at an electron energy
of 30 and 60 MeV, respectively. Taking into considera-
tion the contributions of other reactions with the final-
state copper isotopes, the ratio of the of 67Cu nuclei to
the rest copper isotopes will be still less.
At a 67Cu activity of 0.52 Ci and the target enriched
in 68Zn up to 99%, as well as other conditions being
hold true, the EDR value, ,H
•
determined by the 67Cu
radiation, will be equal to 298 μSv/h. The contribution
from 65Zn will be less than 0.25 μSv/h, and it may be
neglected. The 63Zn (T1/2=38.1 min.) contribution just
after EOB will be ~18 μSv/h. 3 hours later it will be
0.75 μSv/h. The contribution of other isotopes will be
still less, and it may be also disregarded.
As the gamma-radiation of the target includes many
lines, to simplify the calculations, it is reasonable to
unite the adjacent lines. From consideration of the in-
tensity and energy of the gammas (see Table 2), it is
apparent, that the lines of the 64 Cu, 63Zn, 65Zn isotopes
with energy 1 to 1.5 MeV (20.8 % of radiation power)
can be joined into one line, Еγ1=1.2 MeV. The lines of
64Cu, 63Zn, 62Zn, 65Zn, 69Zn with energies between 0.4
and 0.7 MeV (75.7 % of radiation power) can be joined
into the other line, Еγ2=0.55 MeV. In this case, the radi-
ation of 67Cu and the impurities with energy between
0.091 and 0.185 MeV, is no more than 3.5%.
Table 3 lists the values of EDR ( ,H
•
μSv/h) behind
the lead (iron) shield of thickness d at points Ai (see
Figure), contributed by the 100 mCi 67Cu source based
on the irradiated target from natural zinc, and also by
the 0.52 Ci source based on the irradiated target made
from 99% 68Zn-inriched material. In our calculations,
the coefficients U and T, which characterize the protec-
tive barrier type and the personnel occupancy in the
given rooms, were taken from paper [6, 7] and put to
equal 1. The operations with the natural target are as-
sumed to be performed in 3 hours after irradiation.
It is anticipated that the process of the 67Cu isotope
production and the transfers of the irradiated target will
be performed once for every week. In this case the aver-
age dose received by an operator is estimated to be
Нav= Н(А1)+Н(А2))+Н(А3)+Н(А6)+Н(А7) = 0.02+15.6
+ 0.4+8=24 μSv. This being within the established limit
(Table 4).
ISSN 1562-6016. ВАНТ. 2015. №6(100) 162
Table 1
Isotope composition of irradiated Zn- target and their gamma-ray constant
Isotope
Еγ (MeV)
Number of gammas
per one decay
Gamma-ray constant Кγi,
Roent cm2/h·mCi
γ-radiation composition,
%
67Cu
0.091 0.22 0.09 0.57
0.093 0.57 0.25 1.58
0.185 0.22 0.21 1.33
64Cu 1.34 0.005 0.04 0.26
0.51 0.38 1.16 7.37
62Zn
0.041 0.25 - -
0.507 0.15 0.47 2.98
0.51 0.17 0.54 3.43
0.548 0.15 0.47 2.98
0.596 0.26 0.82 5.21
63Zn
0.51 1.85 5.54 35.18
0.669 0.085 0.36 2.29
1.412 0.008 0.06 0.38
0.961 0.07 0.43 2.73
65Zn 0.51 0.031 0.15 0.95
1.115 0.50 2.7 17.14
69mZn 0.439 1 2.45 15.56
0.574 0.03 0.01 0.06
Table 2
Partial activity of the isotopes and EDR from the irradiated Zn- target (R=0.9 m, unshielded)
Isotope Half-life Target activity, mCi
EDR, μSv/h
By the EOB 3 hours after EOB
Natural Enriched Natural Enriched Natural Enriched
67Cu 62.86 h 100 520 57.4 298.7 55.5 289
65Zn 243 days 24.3 0.085 72.3 0.25 72.3 0.25
69mZn 13.7 h 18.3 46.8 40.2
62Zn 9.26 h 186.6 386 308
64Cu 12.7 h 99.8 125.1 106.2
63Zn 0.635 h 1100 3.8 7340 19 278 0.72
Σ 1529 523.9 8023 318 853 290
Table 3
EDR produced by the 67Cu source behind lead (iron) shield of thickness d at reference point Аi
( 00 and 03 hours after irradiation)
Point dPb, cm dFe, cm R, m
100 mCi 67Cu, natural Zn EDR μSv/h 0.52 Ci 67Cu,
enriched Zn
EDR (00), μSv/h EDR (03), μSv/h
А1 14 0.9 0.4 0.033 <0.01
А2 14 0.5 1.3 0.1 <0.01
А7 6 0.9 774 91.6 <0.01
А8 5 0.9 51 3.9 <0.01
А6
5
9
7
0.5
165.2
15.8
47.6
12.7
1.23
3.73
<0.01
<0.01
<0.01
Table 4
Estimates of EDR being received by different organs of the operator at distance R during 67Cu packing procedures
Point dPb, cm Organ, R, m
EDR, μSv/h
Natural zinc, 100 mCi Enriched zinc, 0.52 Ci
А9 1
eyes, 0.5
bone marrow, 0.4
gonads, 0.4
hands, 0.08
1
1.5
1.5
37
5.2
7.8
7.6
1.9
А9 1.5
eyes, 0.5
bone marrow, 0.4
gonads, 0.4
hands, 0.08
0.08
0.12
0.12
3
0.4
0.6
0.6
15
ISSN 1562-6016. ВАНТ. 2015. №6(100) 163
4. ESTIMATION OF RADIATION SHIELD
OF THE LRW TANK
Table 5 gives the main isotopic composition and the
partial activities of impurities in the water phase waste
after the 67Cu extraction from the natural zinc-based
target (12 hours after irradiation). The table gives also
the dependence of the water drain on the period of its
staying in the LRW tank. The next to last column of the
table gives the partial activity of the weekly drain to the
waste water phase, and the last column shows the max-
imum radiation level at a distance of 0.9 m from the
LRW tank.
Table 5
Activity of isotopes produced in one drain run in 1, 2, 3 and 4 weeks after irradiation of natural zinc target,
and the maximum radiation from the LRW tank three months later, at a distance of 0.9 m without shielding
Isotope
Target activity
after 67Cu ex-
traction
1st week
after drain,
mCi
2nd week
after drain,
mCi
3rd week
after drain,
mCi
4th week
after drain,
mCi
Maximum
activity in
the LRW
tank, mCi
Maximum
EDR of the
LRW tank
μSv/h
65Zn 24.28 23.84 23.36 22.9 22.44 260 787
69mZn 16.92 0.002 4·10-7 - - 16.92 43.3
63Zn 0.007 4·10-4 - - - 0.007 0.043
62Zn 149.2 3.8·10-4 - - - 149.2 308.4
Σ 190.4 23.842 23.36 22.9 22.44 426.1 113.8
The thickness of the LRW tank shield was calculat-
ed in the same way like the calculation of the technolog-
ical box shield. In view of change in the isotope activity
ratio and the radiation spectra of the drain water phase,
all radiation lines can be united into two lines, namely,
1.12 and 0.55 MeV. It is shown, that the required shield
thickness is determined by the intensity of the nearby
lines with Еγ =1.12 MeV, and is found to be 9 cm of
lead. For the averaged 0.55 MeV line, the shield thick-
ness will be 3.7 cm, and it can be disregarded. So the
LRW tank must be discharged once in every week.
Then the maximum EDR caused by the 1.12 MeV
gammas at a distance of 0.9 m without shielding will be
71 μSv/h. In this case, the necessary attenuation factor
will make up 17. The lead thickness of 5 cm will be
sufficient to provide the EDR value no higher 4.1 μSv/h.
CONCLUSIONS
At treatment of the photonuclear target from natural
zinc with 100 mCi activity in 67Cu, the technological
box shield made from lead 5 cm thick (or 6 cm thick
iron), as well as the 5 cm lead shield of the LRW tank
provide the radiation environment, which meets stand-
ard requirements. On the first day of the week produc-
tion cycle, when performing procedures to transport the
container with the irradiated target, and also, to extract
67Cu, the operator will receive a dose of 24 μSv. In sub-
sequent four days, the average daily dose will make up
5.5 μSv, and the total annual dose will be 1.26 mSv.
That is much less than the permissible dose limit of
20 mSv. Under those conditions, the radiation risk will
be no more than 7·10-5.
In the case of the enriched zinc target of the same
weight with activity 520 mCi, provided by the same
irradiation mode, the dose received by the operator dur-
ing packing will be distributed as follows: 4.3 μSv/day
for bone marrow and gonads, and 110 μSv/day for
hands (at a norm of 340 μSv/day).
With increase up to 2 cm in the lead thickness of the
container for the separated 67 Cu product, the dose ob-
tained by the hands will be decreased down to
8.5 μSv/day, and the radiation risk will amount 5.6·10-5.
At the use of the enriched target, the productivity of
67Cu is by a factor of 5.2 higher than that for a target of
natural composition. Considering that 1 gram of en-
riched 68Zn and one hour of the accelerator operation
cost $500/g and $200/hour, respectively, the increase in
the yield of the target isotope for a 30-hour cycle will
fully compensate the cost of the target of enriched com-
position.
REFERENCES
1. Manual for reactor produced radioisotopes. IAEA –
TECDOC - 1340, 2003.
2. V. Uvarov, N. Ayzatskiy, N. Dikiy, A. Dovbnya, et al.
Comparison of Cu-67 Production at Cyclotron and
Electron Accelerator // Conf. on Cyclotrons and
their Applications (Cyclotron, Giardini Naxos, Ita-
ly). 2007, p. 224-226.
3. Health Physics / Ed. H.G. Gusev. Moscow:
“Ehnergoatomizdat”, 1989.
4. http//:geant 4. cern.ch.
5. www. Nu Dat 2.6.
6. Basic sanitary rules of radiation safety ensuring in
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2005–09-02. Kiev, 2005.
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electron rules). Moscow, 1988.
Article received 26.10.2015
ISSN 1562-6016. ВАНТ. 2015. №6(100) 164
ОПТИМИЗАЦИЯ УСЛОВИЙ ФОТОЯДЕРНОГО ПРОИЗВОДСТВА 67Cu
А.Н. Довбня, М.А. Должек, Г.Д. Пугачев, О.А. Репихов, А.В. Торговкин, В.Л. Уваров, В.С. Шестакова,
Б.И. Шраменко
Радиофармпрепараты на основе изотопа 67Cu широко используются в иммунотерапии. В сообщении про-
анализированы условия его производства на ускорителе электронов по реакции 68Zn(γ,n)67Cu в отношении
выхода целевого продукта, а также горячих примесей и радиационных рисков. Рассмотрены варианты тех-
нологической мишени массой 40 г из цинка природного состава и обогащенного до 99% по изотопу 68Zn,
активированной тормозным излучением с граничной энергией 30 и 60 МэВ. Показано, что при использова-
нии обогащенной мишени радиационный риск снижается до 10-4, а также значительно уменьшается объем
процедур с отходами.
ОПТИМІЗАЦІЯ УМОВ ФОТОЯДЕРНОГО ВИРОБНИЦТВА 67Cu
А.М. Довбня, М.А. Должек, Г.Д. Пугачев, О.О. Репіхов, О.В. Торговкін, В.Л. Уваров, В.С. Шестакова,
Б.І. Шраменко
Радіофармпрепарати на основі ізотопу 67Cu широко використовуються в імунотерапії. У повідомленні
проаналізовані умови його виробництва на прискорювачі електронів за реакцією 68Zn(γ,n)67Cu відносно ви-
ходу цільового продукту, а також гарячих домішок і радіаційних ризиків. Розглянуто варіанти технологічної
мішені масою 40 г із цинку природного складу і збагаченого до 99% за ізотопом 68Zn, активованою гальмів-
ним випромінюванням із граничною енергією 30 і 60 МеВ. Показано, що при використанні збагаченої міше-
ні радіаційний ризик знижується до 10-4, а також значно зменшується обсяг процедур з відходами.
INTRODUCTION
1. MAIN REACTIONS
2. 67Cu PRODUCTION PROCESS AT THE “ACCELERATOR” Sc&R Est, NSC KIPT
3. ANALYSIS OF ISOTOPE CONTRIBUTION TO EDR
EDR, μSv/h
Isotope
3 hours after EOB
Σ
By the EOB
Point
Point
Isotope
4. ESTIMATION OF RADIATION SHIELD OF THE LRW TANK
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| id | nasplib_isofts_kiev_ua-123456789-112372 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-07T15:28:42Z |
| publishDate | 2015 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Dovbnya, A.N. Dolzhek, M.A. Pugachev, G.D. Repikhov, O.A. Torgovkin, A.V. Uvarov, V.L. Shestakova, V.S. Shramenko, B.I. 2017-01-20T18:10:32Z 2017-01-20T18:10:32Z 2015 Optimization of conditions for ⁶⁷Cu photonuclear production / A.N. Dovbnya, M.A. Dolzhek, G.D. Pugachev, O.A. Repikhov, A.V. Torgovkin, V.L. Uvarov, V.S. Shestakova, B.I. Shramenko // Вопросы атомной науки и техники. — 2015. — № 6. — С. 160-164. — Бібліогр.: 7 назв. — англ. 1562-6016 PACS: 07.85.-m, 81.40wx, 87.53-j, 87.53Wz https://nasplib.isofts.kiev.ua/handle/123456789/112372 Radiopharmaceuticals based on the ⁶⁷Cu isotope have found wide use in immunotherapy. The present paper analyzes the conditions of ⁶⁷Cu production by the ⁶⁸Zn(γ,p) ⁶⁷Cu reaction at an electron accelerator in relation to the target isotope and hot impurities yield, as well as the radiation risks. Consideration has been given to some variants of the technological target 40 g in weight made from natural zinc, and one enriched up to 99% in the ⁶⁸Zn isotope. The target exposition to bremsstrahlung with end-point energy 30 and 60 MeV was studied. It has been found that the use of enriched target results in reduction of both the radiation risk (down to 10⁻⁴) and the scope of waste han-dling procedures. Радіофармпрепарати на основі ізотопу ⁶⁷Cu широко використовуються в імунотерапії. У повідомленні проаналізовані умови його виробництва на прискорювачі електронів за реакцією ⁶⁸Zn(γ,n)⁶⁷Cu відносно виходу цільового продукту, а також гарячих домішок і радіаційних ризиків. Розглянуто варіанти технологічної мішені масою 40 г із цинку природного складу і збагаченого до 99% за ізотопом ⁶⁸Zn, активованою гальмівним випромінюванням із граничною енергією 30 і 60 МеВ. Показано, що при використанні збагаченої мішені радіаційний ризик знижується до 10⁻⁴, а також значно зменшується обсяг процедур з відходами. Радиофармпрепараты на основе изотопа ⁶⁷Cu широко используются в иммунотерапии. В сообщении проанализированы условия его производства на ускорителе электронов по реакции ⁶⁸Zn(γ,n)⁶⁷Cu в отношении выхода целевого продукта, а также горячих примесей и радиационных рисков. Рассмотрены варианты технологической мишени массой 40 г из цинка природного состава и обогащенного до 99% по изотопу ⁶⁸Zn, активированной тормозным излучением с граничной энергией 30 и 60 МэВ. Показано, что при использовании обогащенной мишени радиационный риск снижается до 10⁻⁴, а также значительно уменьшается объем процедур с отходами. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Применение ядерных методов Optimization of conditions for ⁶⁷Cu photonuclear production Оптимізація умов фотоядерного виробництва ⁶⁷Cu Оптимизация условий фотоядерного производства ⁶⁷Cu Article published earlier |
| spellingShingle | Optimization of conditions for ⁶⁷Cu photonuclear production Dovbnya, A.N. Dolzhek, M.A. Pugachev, G.D. Repikhov, O.A. Torgovkin, A.V. Uvarov, V.L. Shestakova, V.S. Shramenko, B.I. Применение ядерных методов |
| title | Optimization of conditions for ⁶⁷Cu photonuclear production |
| title_alt | Оптимізація умов фотоядерного виробництва ⁶⁷Cu Оптимизация условий фотоядерного производства ⁶⁷Cu |
| title_full | Optimization of conditions for ⁶⁷Cu photonuclear production |
| title_fullStr | Optimization of conditions for ⁶⁷Cu photonuclear production |
| title_full_unstemmed | Optimization of conditions for ⁶⁷Cu photonuclear production |
| title_short | Optimization of conditions for ⁶⁷Cu photonuclear production |
| title_sort | optimization of conditions for ⁶⁷cu photonuclear production |
| topic | Применение ядерных методов |
| topic_facet | Применение ядерных методов |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/112372 |
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