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THE ROLE OF A CHOICE 
OF THE TARGET FORM 
FOR 99Tc TRANSMUTATION 
• А.А. Kozar’, 
• V.F. Peretrukhin, 
• K. E. G e r m a n 
• Frumkin Institute of Physical 
Chemistry and Electrochemistry of 
RAS, 
• 31/4 Leninsky prosp., Moscow, 
119071, Russia, 
• kozar@ipc.rssi.ru 
• guerman_k@mail.ru
IT’S WELL KNOWN (SINCE 2000) - 99Tc 
transmutation can be the source of 
artificial stable ruthenium 100–102Ru, the 
second of the mjst interesting elements 
of the Periodic table. 
Such ruthenium has been synthesized 
as a result of a neutron irradiation of Tc 
targets up to 20 – 70 % burn-up 
(for 3 different groups of Tc targets) 
in experiments at SM high-flux reactor 
in 1999 – 2003 .
Russian Tc - Transmutation program (1992-2003) 
------------------------------------------------------------------------------------------------------------------------------------------------------------------------------ 
99Tc(n,g)100Tc(b)100Ru 
75,00% 
50,00% 
25,00% 
0,00% 
= Pessimistic 
0,67 % 
1 2 3 4 5 
Irradiation time, days 
Technetium-99 Burnup, % 
Hanford (USA) 
1989 
Wootan W 
Jordheim DP 
Matsumoto WY 
Petten (NL) 
1994-1998 
Konings RJM 
Franken WMP 
Conrad RP 
et al. 
Dimitrovgrad 
(Russia) 
IPC RAS - NIIAR 
1999 - 2000 
Kozar AA 
Peretroukhine VF 
Tarasov VA et al. 
6% 
18% 
34% 
65% 
10.5 days 
193 days 579 days 72 days 260 days 
2
Tc transmutation experiment (IPCE RAS – NIIAR, 1999-2008) 
In IPC RAS a set of metal disc targets (10x10x0.3 mm) prepared 
and assembled in two batches with total weight up to 5 g. 
Transmutation experiment was carried out at high flux 
SM-3 reactor ( NIIAR, Dimitrovgrad ) 
2nd batch: Ft > 2 1015 cm-2s-1 
1st batch: Ft=1.3 1015 cm-2s-1 
99Tc burnups have made: 
34  6 % and 65  11 % 
for the 1st and 2nd targets batches 
---- 
 The high 99Tc burn-ups were 
reached and about 2.5 g of new 
matter - transmutation ruthenium 
were accumulated as a result of 
experiments on SM-3 reactor 
 These values are significantly 
higher of burnups 6 and 16 % 
achieved on HFR in Petten earlier 
9 12 
96 86 76 66 56 46 
КО3 КО4 
95 85 75 65 55 45 
94 84 54 44 
93 83 53 43 
92 82 72 62 52 42 
81 71 61 51 41 
КО1 
91 
КО2 
3 
7 
АР 
2 
Д-9 
1  центральный блок трансурановых мишеней; 2  бериллиевые вкладыши; 
3  бериллиевые блоки отражателя; 4  центральный компенсирующий орган 
7 Д-2  канал и его номер 81 
 автоматический регулятор 
 ячейка активной зоны с Т ВС 
 стержень аварийной защиты 
 компенсирующий орган 
91 
КО- 
2 
АР 
1 
4 
3 
2 
1 
Д-3 Д-1 
Д-2 
2 
6 
15 14 
16 8 
Д-4 
Д-5 
17 
Д-6 
Д-10 
13 
Д-8 
АР1 
19 
4 
10 
Д-7 
5 
20 
18 11 21 
Рис.5. Картограмма реактора СМ 
2
IRRADIATION OF 99Tc METAL TARGETS 
IN NUCLEAR HIGH FLUX REACTORS 
Petten transmutation experiment 
99Tc targets: metal cylinders Ø 4.8 mm and with height 
of 25 mm 
99Tc burn-up in Petten reactor are 6 % (T1) and 16 – 
18 % (T2). 
Dimitrovgrad transmutation experiment on SM high-flux 
reactor 
99Tc targets: metal disks Ø 6.0  0.3 mm and with 
thickness of 0.3  0.02 mm 
Total targets mass is 10 g 
3
99Tc BURN-UP AND HALF-CONVERSION PERIOD 
Measured and calculated 99Tc burn-up and half-conversion periods in SM reactor. 
№ of 
group 
Burn-up, % Irradiation 
time, 
eff. days 
Half-conversion 
period , 
burn T 2 / 1 
measured calculated eff. days 
1 192 202 72.7 240 
2 453 505 262.7 305 
3 705 707 424.8 245 
99Tc burn-up in Petten reactor are 6 % (T1) 
and 16 – 18 % (T2). 
99Tc half-conversion period 
 2160 eff. days. burn T 1/ 2 
Fig. 2. Calculated dependence of 99Tc burn-up on 
irradiation time () and its experimental values 
() for 3 groups of targets. 
4
ARTIFICIAL Ru ACTIVITY DECAY 
Actinide content in Tc: 5•10–8 g An per g of Tc (better values are expensive!) 
Actinide fission product 106Ru (T1/2=371.6 days) can’t be separated from artificial 
Ru by chemical methods. 
Activity of 106Ru + 106Rh in artificial Ru 
b - , 371.6 days b - , 29.8 sec 
106Ru (pure b -radiator, γ is absent)  106Rh  106Pd (stable) 
106Rh has 2 main g -lines with energies 511.8 keV and 621.8 keV 
In 2006 106Rh activity in Ru from 20 % burn-up targets later  2100 days {5.7 T1/2 (106Ru)} 
after irradiation stop: 
106 A 
15  2 Bk/g of Ru  total activity of pair 106Ru + 106Rh  30 Bk/g of Ru 
1 
lim A 
106 A 
Later 10 years after irradiation stop: = 3.2  0.4 Bk/g of Ru < = 3.7 Bk/g  
 Since 2010 artificial Ru from 20% burn-up targets can 
be used without limitation 
Artificial Ru separated from 45 % and 70 % burn-up targets can be 
used in non-nuclear industry 9 and 8 years after synthesis 
correspondingly 
5
ARTIFICIAL STABLE RUTHENIUM PURIFICATION FROM 106Ru 
Relative yield Y of 106Ru nuclei recoiling from spherical 
grains of technetium powder, in dependence on their 
diameter D (average fission-fragment path length is about 
8 microns). 
6
Transformation of disks Ø 6 mm × 0.3 mm in 
cylindrical targets Ø 6 mm × 6 mm 
Fig. 4. Relative position of Tc (Tc-Ru) grains in heterogeneous target. 
7
Possible target chemical substances 
• Tc Metal - Tc 
• Tc Carbide - Tc6C 
• Tc Dioxide - TcO2 
• Tc Disulfide - TcS2 
• and its mixtures with inert matter 
8
Target substances 
1. Metal 
Instrumentation 
• Furnaces 
• 6% H2|Ar 
industurial 
balloon mixture 
• Ingots 
• Rolling-mill 
• et cetera… 
Sample type : 
• Ordinary 
Powder 
metal 
• Fused 
metal 
• Single 
crystal 
• Foil 
Starting 
material : 
• TcO2 
• NH4TcO4 
• R4NTcO4 
9
1. Bulk Tc metal 
11 
• Set-up used for fusion and casting of Tc metal 
• Single crystal Tc metal
1. Tc metal – foil, X-ray study 
• d: 20 micrometers 
• Systematic absence of X-ray reflex 
• = Preferential orientation of crystallites with C 
axe perpendicular to the foil surface 
12
1. Tc metal – foil, assembling 
13 
• Spacer grid-bush with 99Tc targets (1) and 
aluminium core (2) of capsule for loading 
in reactor.
1. Tc metal – foil 
chemical consequences 
• Dissolution in HNO3 dramatically slowed-down 
starting from 20% Tc to Ru conversion 
• Possible to increase the dissolution rate by 
aggressive agents addition (Ag2+, IO4 
-) but 
corrosion problems arises 
• Possibly the best reprocessing procedure – 
burning in O2 – not approved by industry to date 
12
Target substances 
2. Tc Carbide 
• Orthorhombic Tc metal is formed at low C content 
Grey bars : ref. hcp Tc metal 
Curves : exp. spectra 
30 40 50 60 70 80 90 
100 
75 
50 
25 
100 
75 
50 
25 
0 
30 40 50 60 70 80 90 
0 
B 
I, % 
2Theta, deg 
A 
I, %
Target substances 
2. Tc Carbide 
• Tc6C – non-stoechiometry 
• Tc6C + nC excess carbon for no slowing-down 
• Tc6C – formed by : 
• Tc + C reaction 
• Tc + C6H6 
• R4NTcO4 thermal 
decomposition in Ar
Target substances – Tc carbide 
2. Tc6C + nC excess carbon 
• EXAFS study of 
Tc6C + nC [1] – 
wavelet 
presentation 
[1] K.German, Ya.Zubavichus ISTR2011
1. Tc carbide 
chemical consequences 
• Dissolution of Tc is more active as no RuC is known 
and so it is’nt formed during transmutation of Tc 
carbide to Ru - Tc and Ru being stabilized in 
separate phases 
• Drawback: Possible mechanical inclusions of Tc in 
Ru residue at high burn-ups 
• Mixtures with C excess could be the best choice 
because resonance energy neutrons are 
participating in transmutation due to enhanced 
thermolisation inside the target 
12
1. Tc dioxide 
chemical consequences 
• Preparation by chemical reduction – high impurity 
content 
• Preparation from NH4TcO4 – similar to Tc metal 
• Target instability due to excess O released (Ru is 
stabilised as metal) 
• Some Tc2O7 formed at high burn-up 
• This target material is not recommended 
12
Preparation of artificial stable Ruthenium by 
transmutation of Technetium 
• New Ruthenium is almost 
monoisotopic Ru-100, it has 
different spectral properties 
• It is available only to several 
countries that develop nuclear 
industry 
 Tc target material: 
 Tc metal powder / Kozar 
(2008) 
 Tc – C composite Tc carbide 
/ German (2005) 
 Rotmanov K. et all. 
Radiochemistry, 50 (2008) 
408 :
Conclusions 
• 99Tc transmutation can be the source of artificial 
stable ruthenium 100–102Ru. 
• Metal homogeneous Tc targets are possible 
• Tc carbide targets are favorabale 
• Artificial ruthenium demanded exposure during 8 – 
10 years for application without restrictions 
• Application of heterogeneous targets with nuclear-inert 
stuff to reduce a 106Ru radioactivity in artificial 
Ru 
• The target form effect the artificial ruthenium purity 
at equal Tc nuclear density in irradiated volume.
• Transformation of disks in cylinders in the conditions of identical 
irradiated volume could allow to lower 106Ru concentration in artificial 
ruthenium. The minimum fission-fragment path length in Tc metal 
makes about 5 microns (average fission-fragment path length is about 8 
microns). The corresponding form of a heterogeneous target is a tablet 
consisting of a mix of spherical Tc metal particle in diameter of 5 
microns and a nuclear-inert stuff with Tc average density which in 20 
times is less, than Tc metal. In this case all fission-fragments, including 
106Ru, escape the Tc (Tc-Ru) grains to stuff. The average distance 
between Tc spherical grains is about 23 microns, between their surfaces 
is about 18 microns at regular distribution of Tc particles in a target. 
• Fission-fragment path length in the most applicable nuclear-inert 
materials (such as ZrO2, Y2O3, MgAl2O4, MgO, Y3Al5O12, SiC, Al2O3, ZrO2- 
Y2O3, ZrO2-CaO and many others) makes 12 – 15 microns, hence hit 
probability of 106Ru fission-fragments in the next Tc grain is negligibly 
small. Artificial ruthenium from such target would be almost free from 
106Ru nuclei. Additional purification of commercial Tc from actinide 
impurities would be not necessary at a choice of such target form 
instead of metal disks. In this case artificial ruthenium could be applied 
in non-nuclear field through 3 – 3.5 years after an irradiation, necessary 
to decay of transmutation product 103Ru (T1/2 = 39.3 days).
• References 
• 1. V. Peretroukhine, V. Radchenko, A. Kozar’ et al. Technetium 
transmutation and production of artifical stable ruthenium. // Comptes 
Rendus. – Ser. Chimie. – 2004. – Tome 7. – Fascicule 12. – P. 1215 – 
1218. 
• 2. А.А. Kozar’, V.F. Peretroukhin, K.Vразличные химические методы, а 
ские методы, а общий технеций, ка мишеналла рутения 
трансмутацией . Rotmanov, V.A. Tarasov. The elaboration of technology 
bases for the artificial stable ruthenium preparation from technetium- 
99 transmutation products. // 7th International Symposium on 
Technetium and Rhenium – Science and Utilization. Moscow, Russia, 
July 4 – 8, 2011. – Book of Proceedings. – P. 113. – Publishing House 
GRANITSA, Moscow, 2011. – 460 p. 
• 3. А.А. Kozar’, V.F. Peretroukhin, K.Vразличные химические методы, а 
ские методы, а общий технеций, ка мишеналла рутения 
трансмутацией . Rotmanov, V.A. Tarasov. The elaboration of technology 
bases for the artificial stable ruthenium preparation from technetium- 
99 transmutation products. // Ibid. – P. 113.
Thank you 
for the attention !

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2014 german-kozar-transmutation istr

  • 1. THE ROLE OF A CHOICE OF THE TARGET FORM FOR 99Tc TRANSMUTATION • А.А. Kozar’, • V.F. Peretrukhin, • K. E. G e r m a n • Frumkin Institute of Physical Chemistry and Electrochemistry of RAS, • 31/4 Leninsky prosp., Moscow, 119071, Russia, • kozar@ipc.rssi.ru • guerman_k@mail.ru
  • 2. IT’S WELL KNOWN (SINCE 2000) - 99Tc transmutation can be the source of artificial stable ruthenium 100–102Ru, the second of the mjst interesting elements of the Periodic table. Such ruthenium has been synthesized as a result of a neutron irradiation of Tc targets up to 20 – 70 % burn-up (for 3 different groups of Tc targets) in experiments at SM high-flux reactor in 1999 – 2003 .
  • 3. Russian Tc - Transmutation program (1992-2003) ------------------------------------------------------------------------------------------------------------------------------------------------------------------------------ 99Tc(n,g)100Tc(b)100Ru 75,00% 50,00% 25,00% 0,00% = Pessimistic 0,67 % 1 2 3 4 5 Irradiation time, days Technetium-99 Burnup, % Hanford (USA) 1989 Wootan W Jordheim DP Matsumoto WY Petten (NL) 1994-1998 Konings RJM Franken WMP Conrad RP et al. Dimitrovgrad (Russia) IPC RAS - NIIAR 1999 - 2000 Kozar AA Peretroukhine VF Tarasov VA et al. 6% 18% 34% 65% 10.5 days 193 days 579 days 72 days 260 days 2
  • 4. Tc transmutation experiment (IPCE RAS – NIIAR, 1999-2008) In IPC RAS a set of metal disc targets (10x10x0.3 mm) prepared and assembled in two batches with total weight up to 5 g. Transmutation experiment was carried out at high flux SM-3 reactor ( NIIAR, Dimitrovgrad ) 2nd batch: Ft > 2 1015 cm-2s-1 1st batch: Ft=1.3 1015 cm-2s-1 99Tc burnups have made: 34  6 % and 65  11 % for the 1st and 2nd targets batches ----  The high 99Tc burn-ups were reached and about 2.5 g of new matter - transmutation ruthenium were accumulated as a result of experiments on SM-3 reactor  These values are significantly higher of burnups 6 and 16 % achieved on HFR in Petten earlier 9 12 96 86 76 66 56 46 КО3 КО4 95 85 75 65 55 45 94 84 54 44 93 83 53 43 92 82 72 62 52 42 81 71 61 51 41 КО1 91 КО2 3 7 АР 2 Д-9 1  центральный блок трансурановых мишеней; 2  бериллиевые вкладыши; 3  бериллиевые блоки отражателя; 4  центральный компенсирующий орган 7 Д-2  канал и его номер 81  автоматический регулятор  ячейка активной зоны с Т ВС  стержень аварийной защиты  компенсирующий орган 91 КО- 2 АР 1 4 3 2 1 Д-3 Д-1 Д-2 2 6 15 14 16 8 Д-4 Д-5 17 Д-6 Д-10 13 Д-8 АР1 19 4 10 Д-7 5 20 18 11 21 Рис.5. Картограмма реактора СМ 2
  • 5. IRRADIATION OF 99Tc METAL TARGETS IN NUCLEAR HIGH FLUX REACTORS Petten transmutation experiment 99Tc targets: metal cylinders Ø 4.8 mm and with height of 25 mm 99Tc burn-up in Petten reactor are 6 % (T1) and 16 – 18 % (T2). Dimitrovgrad transmutation experiment on SM high-flux reactor 99Tc targets: metal disks Ø 6.0  0.3 mm and with thickness of 0.3  0.02 mm Total targets mass is 10 g 3
  • 6. 99Tc BURN-UP AND HALF-CONVERSION PERIOD Measured and calculated 99Tc burn-up and half-conversion periods in SM reactor. № of group Burn-up, % Irradiation time, eff. days Half-conversion period , burn T 2 / 1 measured calculated eff. days 1 192 202 72.7 240 2 453 505 262.7 305 3 705 707 424.8 245 99Tc burn-up in Petten reactor are 6 % (T1) and 16 – 18 % (T2). 99Tc half-conversion period  2160 eff. days. burn T 1/ 2 Fig. 2. Calculated dependence of 99Tc burn-up on irradiation time () and its experimental values () for 3 groups of targets. 4
  • 7. ARTIFICIAL Ru ACTIVITY DECAY Actinide content in Tc: 5•10–8 g An per g of Tc (better values are expensive!) Actinide fission product 106Ru (T1/2=371.6 days) can’t be separated from artificial Ru by chemical methods. Activity of 106Ru + 106Rh in artificial Ru b - , 371.6 days b - , 29.8 sec 106Ru (pure b -radiator, γ is absent)  106Rh  106Pd (stable) 106Rh has 2 main g -lines with energies 511.8 keV and 621.8 keV In 2006 106Rh activity in Ru from 20 % burn-up targets later  2100 days {5.7 T1/2 (106Ru)} after irradiation stop: 106 A 15  2 Bk/g of Ru  total activity of pair 106Ru + 106Rh  30 Bk/g of Ru 1 lim A 106 A Later 10 years after irradiation stop: = 3.2  0.4 Bk/g of Ru < = 3.7 Bk/g   Since 2010 artificial Ru from 20% burn-up targets can be used without limitation Artificial Ru separated from 45 % and 70 % burn-up targets can be used in non-nuclear industry 9 and 8 years after synthesis correspondingly 5
  • 8. ARTIFICIAL STABLE RUTHENIUM PURIFICATION FROM 106Ru Relative yield Y of 106Ru nuclei recoiling from spherical grains of technetium powder, in dependence on their diameter D (average fission-fragment path length is about 8 microns). 6
  • 9. Transformation of disks Ø 6 mm × 0.3 mm in cylindrical targets Ø 6 mm × 6 mm Fig. 4. Relative position of Tc (Tc-Ru) grains in heterogeneous target. 7
  • 10. Possible target chemical substances • Tc Metal - Tc • Tc Carbide - Tc6C • Tc Dioxide - TcO2 • Tc Disulfide - TcS2 • and its mixtures with inert matter 8
  • 11. Target substances 1. Metal Instrumentation • Furnaces • 6% H2|Ar industurial balloon mixture • Ingots • Rolling-mill • et cetera… Sample type : • Ordinary Powder metal • Fused metal • Single crystal • Foil Starting material : • TcO2 • NH4TcO4 • R4NTcO4 9
  • 12. 1. Bulk Tc metal 11 • Set-up used for fusion and casting of Tc metal • Single crystal Tc metal
  • 13. 1. Tc metal – foil, X-ray study • d: 20 micrometers • Systematic absence of X-ray reflex • = Preferential orientation of crystallites with C axe perpendicular to the foil surface 12
  • 14. 1. Tc metal – foil, assembling 13 • Spacer grid-bush with 99Tc targets (1) and aluminium core (2) of capsule for loading in reactor.
  • 15. 1. Tc metal – foil chemical consequences • Dissolution in HNO3 dramatically slowed-down starting from 20% Tc to Ru conversion • Possible to increase the dissolution rate by aggressive agents addition (Ag2+, IO4 -) but corrosion problems arises • Possibly the best reprocessing procedure – burning in O2 – not approved by industry to date 12
  • 16. Target substances 2. Tc Carbide • Orthorhombic Tc metal is formed at low C content Grey bars : ref. hcp Tc metal Curves : exp. spectra 30 40 50 60 70 80 90 100 75 50 25 100 75 50 25 0 30 40 50 60 70 80 90 0 B I, % 2Theta, deg A I, %
  • 17. Target substances 2. Tc Carbide • Tc6C – non-stoechiometry • Tc6C + nC excess carbon for no slowing-down • Tc6C – formed by : • Tc + C reaction • Tc + C6H6 • R4NTcO4 thermal decomposition in Ar
  • 18. Target substances – Tc carbide 2. Tc6C + nC excess carbon • EXAFS study of Tc6C + nC [1] – wavelet presentation [1] K.German, Ya.Zubavichus ISTR2011
  • 19. 1. Tc carbide chemical consequences • Dissolution of Tc is more active as no RuC is known and so it is’nt formed during transmutation of Tc carbide to Ru - Tc and Ru being stabilized in separate phases • Drawback: Possible mechanical inclusions of Tc in Ru residue at high burn-ups • Mixtures with C excess could be the best choice because resonance energy neutrons are participating in transmutation due to enhanced thermolisation inside the target 12
  • 20. 1. Tc dioxide chemical consequences • Preparation by chemical reduction – high impurity content • Preparation from NH4TcO4 – similar to Tc metal • Target instability due to excess O released (Ru is stabilised as metal) • Some Tc2O7 formed at high burn-up • This target material is not recommended 12
  • 21. Preparation of artificial stable Ruthenium by transmutation of Technetium • New Ruthenium is almost monoisotopic Ru-100, it has different spectral properties • It is available only to several countries that develop nuclear industry  Tc target material:  Tc metal powder / Kozar (2008)  Tc – C composite Tc carbide / German (2005)  Rotmanov K. et all. Radiochemistry, 50 (2008) 408 :
  • 22. Conclusions • 99Tc transmutation can be the source of artificial stable ruthenium 100–102Ru. • Metal homogeneous Tc targets are possible • Tc carbide targets are favorabale • Artificial ruthenium demanded exposure during 8 – 10 years for application without restrictions • Application of heterogeneous targets with nuclear-inert stuff to reduce a 106Ru radioactivity in artificial Ru • The target form effect the artificial ruthenium purity at equal Tc nuclear density in irradiated volume.
  • 23. • Transformation of disks in cylinders in the conditions of identical irradiated volume could allow to lower 106Ru concentration in artificial ruthenium. The minimum fission-fragment path length in Tc metal makes about 5 microns (average fission-fragment path length is about 8 microns). The corresponding form of a heterogeneous target is a tablet consisting of a mix of spherical Tc metal particle in diameter of 5 microns and a nuclear-inert stuff with Tc average density which in 20 times is less, than Tc metal. In this case all fission-fragments, including 106Ru, escape the Tc (Tc-Ru) grains to stuff. The average distance between Tc spherical grains is about 23 microns, between their surfaces is about 18 microns at regular distribution of Tc particles in a target. • Fission-fragment path length in the most applicable nuclear-inert materials (such as ZrO2, Y2O3, MgAl2O4, MgO, Y3Al5O12, SiC, Al2O3, ZrO2- Y2O3, ZrO2-CaO and many others) makes 12 – 15 microns, hence hit probability of 106Ru fission-fragments in the next Tc grain is negligibly small. Artificial ruthenium from such target would be almost free from 106Ru nuclei. Additional purification of commercial Tc from actinide impurities would be not necessary at a choice of such target form instead of metal disks. In this case artificial ruthenium could be applied in non-nuclear field through 3 – 3.5 years after an irradiation, necessary to decay of transmutation product 103Ru (T1/2 = 39.3 days).
  • 24. • References • 1. V. Peretroukhine, V. Radchenko, A. Kozar’ et al. Technetium transmutation and production of artifical stable ruthenium. // Comptes Rendus. – Ser. Chimie. – 2004. – Tome 7. – Fascicule 12. – P. 1215 – 1218. • 2. А.А. Kozar’, V.F. Peretroukhin, K.Vразличные химические методы, а ские методы, а общий технеций, ка мишеналла рутения трансмутацией . Rotmanov, V.A. Tarasov. The elaboration of technology bases for the artificial stable ruthenium preparation from technetium- 99 transmutation products. // 7th International Symposium on Technetium and Rhenium – Science and Utilization. Moscow, Russia, July 4 – 8, 2011. – Book of Proceedings. – P. 113. – Publishing House GRANITSA, Moscow, 2011. – 460 p. • 3. А.А. Kozar’, V.F. Peretroukhin, K.Vразличные химические методы, а ские методы, а общий технеций, ка мишеналла рутения трансмутацией . Rotmanov, V.A. Tarasov. The elaboration of technology bases for the artificial stable ruthenium preparation from technetium- 99 transmutation products. // Ibid. – P. 113.
  • 25. Thank you for the attention !