Innovative Approach to Radioisotope Production Using IFMIF-DONES Neutron Source
Assessment of radioisotopes production in IFMIF-DONES Test Cell
F.Mota*, M.I. Ortiz, E. López-Melero, I. Porras, J. Praena
F.Mota*, M.I. Ortiz, E. López-Melero, I. Porras, J. Praena
, M. Alcantud, N. Ballesteros, A. Dilla, E.
Fernández, J.Gallo, J.C. Marugan, C. Prieto, I. Cobo, O. Oliva, D. Terán
Index
1.
Why use IFMIF-DONES for Radioisotope production
2.
Assessment of the
99
Mo production in IFMIF-DONES
3.
High level requirements of the RadioIsotope Production Device (RIPD)
4.
Proposals of concepts design for the RIPD
5.
99
Mo assessment production considering the first RIPD mockups
6.
Radioisotope production device vs Neutron Spectral Shifter
7.
Conclusions and Future works
Index
1.
Why use IFMIF-DONES for Radioisotope production
2.
Assessment of the
99
Mo production in IFMIF-DONES
3.
High level requirements of the RadioIsotope Production Device (RIPD)
4.
Proposals of concepts design for the RIPD
5.
99
Mo assessment production considering the first RIPD mockups
6.
Radioisotope production device vs Neutron Spectral Shifter
7.
Conclusions and Future works
99
Mo is the precursor of
Technetium-99m (
99m
Tc), which is used for radiopharmaceutical applications
However, a global shortage of
99
Mo emerged in the late 2000s
because of the frequent shut down due to
extended maintenance periods of the main reactors for
99
Mo
production: NRU Chalk River Reactor (Canada)
and the High Flux Reactor (HFR) at Petten (The Netherlands).
99
Mo is
currently produced in nuclear fission reactors as a by-product of
235
U fission.
Why use IFMIF-DONES for Radioisotope production
However the
100
Mo(n,2n)
99
Mo
cross section has a threshold energy at about
7 MeV then this way of
production is not reached by conventional reactors.
Neutron Energy of Fission below 7 MeV
An alternative of
235
U
fission method is to irradiate directly Molybdenum to produce
99
Mo
. It is produced by
two ways the
98
Mo(n,
γ
)
99
Mo
and
100
Mo(n,2n)
99
Mo
reactions.
DONES neutron source up to 55 MeV
98
Mo
(
n,
γ)
99
Mo
100
Mo
(
n, 2n
)
99
Mo
1.17 %
98.83 %
Ratio
Taking into account that only there is a 9.82 % of
100
Mo in a natural composition, higher amount of
99
Mo could be obtained enriching the Molybdenum
in
100
M.
98
Mo
(
n,
γ)
99
Mo
100
Mo
(
n, 2n
)
99
Mo
1.17 %
98.83 %
Ratio
Taking into account that only there is a 9.82 % of
100
Mo in a natural composition, higher amount of
99
Mo could be obtained enriching the Molybdenum
in
100
M.
Why use IFMIF-DONES for Radioisotope production
Index
1.
Why use IFMIF-DONES for Radioisotope production
2.
Assessment of the
99
Mo production in IFMIF-DONES
3.
High level requirements of the RadioIsotope Production Device (RIPD)
4.
Proposals of concepts design for the RIPD
5.
99
Mo assessment production considering the first RIPD mockups
6.
Radioisotope production device vs Neutron Spectral Shifter
7.
Conclusions and Future works
Irradiation time determination of the molybdenum samples of MoO
3
After 6 days of irradiation the sample is extracted from the TC to be purified and then transported outer the IFMIF-DONES
installation
After 6 days of irradiation the sample is extracted from the TC to be purified and then transported outer the IFMIF-DONES
installation
Assessment of the
99
Mo production in IFMIF-DONES
The
100
Mo(n,2n) and
98
Mo(n,γ) reaction have been
taken into account for the
99
Mo production
“
T
he
(
n,
γ)
process produces 99Mo of relatively low specific activity, from a low of 3.7 GBq/g to a high of 74
GBq/g depending on the neutron flux available in the reactor”.
The
100
Mo(n,2n) and
98
Mo(n,γ) reaction have been
taken into account for the
99
Mo production
“
T
he
(
n,
γ)
process produces 99Mo of relatively low specific activity, from a low of 3.7 GBq/g to a high of 74
GBq/g depending on the neutron flux available in the reactor”.
Assessment for
99
Mo production in the TC area
Assessment of the 99Mo production in IFMIF-DONES
~8 cm
20 cm
Considering an average production of 44 GBq/g in the Mesh and
taking into account a density of 3.17 g/cm
3
of Mo in
4.69
g/c
m
3
of
100
MoO3 and mesh volume of 100 cm
3
, the total activity reached of
99
Mo would be about 14 TBq after 6
days of irradiation
.
It would supply
99
Mo generators to cover the demand of Andalucía
(
100 GBq per
99m
Tc generator
)
Sensitivity analysis of the
99
Mo production behind of HFTM
Mesh used for Neutron spectra calculation
Assessment of the
99
Mo production in IFMIF-DONES
High level requirements of the RadioIsotope Production Device (RIPD)
1.
Do not disturb the normal operation of the IFMIF-DONES.
2.
The targets should be introduced and extracted in periods of 6-day without opening the TC
3.
Automatic insertion and extraction of targets
•
mechanical or pneumatic extraction and insertion
•
Lateral or vertical access
6.
To keep the integrity of the TC shielding
7.
The target has to be solid or encapsulated to avoid contamination
7.
Maximization of the irradiation volume to maximize the production rate.
8.
The handling of the targets has to be done remotely.
9.
The system must be cooled to maintain a constant temperature during irradiation
.
10.
Having an Hot Cell for handling irradiated targets
.
11.
To define specific safety protocols to insertion, extraction, purification and introduction in generators to be exported to
Hospitals and research centers.
Index
1.
Why use IFMIF-DONES for Radioisotope production
2.
Assessment of the
99
Mo production in IFMIF-DONES
3.
High level requirements of the RadioIsotope Production Device (RIPD)
4.
Proposals of concepts design for the RIPD
5.
99
Mo assessment production considering the first RIPD mockups
6.
Radioisotope production device vs Neutron Spectral Shifter
7.
Conclusions and Future works
Transverse duct for sample
Shielding plug
during samples
extraction
Shielding plug during
irradiation
Proposals of EAI (to meet with the high level requirements)
Proposals of concepts design for the RIPD
100
Mo sample holder
Ø =20 cm
The dimensions of each plate is 0.9x27.5x11.4 cm
3
. (
V=282.15 cm
3
)
The dimensions of each plate is 0.9x27.5x11.4 cm
3
. (
V=282.15 cm
3
)
Ø =28.5 cm
The sealing of the inner of the TC is kept
R158
Based on the Japanese proposal (O. Nasayiuki, FED 2021))
PROPOSAL 1: lateral mechanical sample insertion device for Radioisotope production
Proposals of concepts design for the RIPD
PROPOSAL 2: lateral sample insertion using a Rabbit system
Transference table
Transverse duct for sample
Spherical specimens of 10.5 mm diameter
Inside the duct there are several smaller ducts to transport the
spherical specimens. Inner diameter of the duct could be 13 mm
Index
1.
Why use IFMIF-DONES for Radioisotope production
2.
Assessment of the
99
Mo production in IFMIF-DONES
3.
High level requirements of the RadioIsotope Production Device (RIPD)
4.
Proposals of concepts design for the RIPD
5.
99
Mo assessment production considering the first RIPD mockups
6.
Radioisotope production device vs Neutron Spectral Shifter
7.
Conclusions and Future works
D
+
D
+
Shielding
The dimensions of each plate is 0.9x27.5x11.4 cm
3
. (
V=282.15 cm
3
)
The length from HFTM to the Radioisotope Production Device is 1.3 cm
The length from HFTM to the first
100
MO
3
plate is 8 cm
The distance between
100
MoO
3
plates is 1.1 cm
Neutron transport calculations performed to determine the
99
Mo production rate considering proposal 1
99
Mo assessment production considering the first RIPD mockups
99
Mo activity obtained in each plate after 6 days of irradiation
using an average neutron fluence rate in each plate.
1 2 3 4
Considering that
one
99m
Tc generation
has about an activity of
46 GBq,
which could be equivalent to considering
a 100 GBq
just before taking out the sample.
99
Mo assessment production considering the first RIPD mockups
Under these conditions, it is possible to produce
~
69.80 TBq de
99
Mo/
99m
Tc, per week
It means that we could obtain about
700 generators per week
Taking into account that a hospital could need 2 generators per
week, we could supply to 350 hospitals.
Index
1.
Why use IFMIF-DONES for Radioisotope production
2.
Assessment of the
99
Mo production in IFMIF-DONES
3.
High level requirements of the RadioIsotope Production Device (RIPD)
4.
Proposals of concepts design for the RIPD
5.
99
Mo assessment production considering the first RIPD mockups
6.
Radioisotope production device vs Neutron Spectral Shifter
7.
Conclusions and Future works
The Radioisotope production device could have a similar effect like the Neutron Spectral shifter module (NSS) due to the
100
Mo(n,2n)
99
Mo
reaction
Radioisotope production device vs Neutron Spectral Shifter
D
+
Index
1.
Why use IFMIF-DONES for Radioisotope production
2.
Assessment of the
99
Mo production in IFMIF-DONES
3.
High level requirements of the RadioIsotope Production Device (RIPD)
4.
Proposals of concepts design for the RIPD
5.
99
Mo assessment production considering the first RIPD mockups
6.
Radioisotope production device vs Neutron Spectral Shifter
7.
Conclusions and Future works
Conclusions and Future works
A
99
Mo production assessment has been performed in IFMIF-DONES TC taking in advance the neutrons
that cross the HFTM.
Two mock-ups for the Radioisotope production devices have been proposed.
Considering the mechanical insertion proposal conditions, it would be possible to cover the necessities of 350
hospitals of
~
99
Mo/
99m
Tc
per week.
per week.
The works are ongoing to validate the different RIPD concepts proposed respect to the productions
rates, radiation hazards, safety issues and design analysis.
Then, the benefit of radioisotope production in IFMIF-DONES has been demonstrated starting from the
assessment production of one of the most demanding radioisotopes for cancer diagnostics. This could
mean a great social benefit since the demand of a large number of inhabitants could be covered and a
great benefit for IFMIF-DONES project, on the one hand for its social impact and on the other because it
could mean important funding for IFMIF-DONES operation.
An assessment on the production of radioisotopes in the IFMIF-DONES test cell highlights the significance of 99Mo, the precursor of Technetium-99m used in radiopharmaceutical applications. The global shortage of 99Mo due to reactor maintenance issues has led to the exploration of alternative methods such as direct irradiation of Molybdenum. The IFMIF-DONES neutron source offers a promising solution with unique features for enhanced imaging and reduced patient radiation dose, presenting a potential shift from conventional production methods. The study delves into the necessity, challenges, and proposals for efficient radioisotope production in the medical field.
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Presentation Transcript
Assessment of radioisotopes production in IFMIF-DONES Test Cell F.Mota*, M.I. Ortiz, E. L pez-Melero, I. Porras, J. Praena, M. Alcantud, N. Ballesteros, A. Dilla, E. Fern ndez, J.Gallo, J.C. Marugan, C. Prieto, I. Cobo, O. Oliva, D. Ter n
Index 1. Why use IFMIF-DONES for Radioisotope production 2. Assessment of the 99Mo production in IFMIF-DONES 3. High level requirements of the RadioIsotope Production Device (RIPD) 4. Proposals of concepts design for the RIPD 99Mo assessment production considering the first RIPD mockups 5. 6. Radioisotope production device vs Neutron Spectral Shifter 7. Conclusions and Future works
Index 1. Why use IFMIF-DONES for Radioisotope production 2. Assessment of the 99Mo production in IFMIF-DONES 3. High level requirements of the RadioIsotope Production Device (RIPD) 4. Proposals of concepts design for the RIPD 99Mo assessment production considering the first RIPD mockups 5. 6. Radioisotope production device vs Neutron Spectral Shifter 7. Conclusions and Future works
Why use IFMIF-DONES for Radioisotope production 99Mo is the precursor of Technetium-99m (99mTc), which is used for radiopharmaceutical applications on 99m 99mTc are Tc are used Radiopharmaceuticals Radiopharmaceuticals based procedures per year, accounting for about 85% of all nuclear medicine procedures per year, accounting for about 85% of all nuclear medicine diagnostics diagnostics based on used in more in more than 30 million than 30 million 99m 99mTc are Tc are used to its short half to its short half- -life T1/2 (6 h) and the 140 life T1/2 (6 h) and the 140 keV used in Single Photon Emission Computed Tomography (SPECT) Thanks in Single Photon Emission Computed Tomography (SPECT) Thanks keV - -ray emission ray emission Ideal features for imaging and low radiation dose to the patient Ideal features for imaging and low radiation dose to the patient 99Mo is currently produced in nuclear fission reactors as a by-product of 235U fission. However, a global shortage of99Mo emerged in the late 2000s because of the frequent shut down due to extended maintenance periods of the main reactors for99Mo production: NRU Chalk River Reactor (Canada) and the High Flux Reactor (HFR) at Petten (The Netherlands).
Why use IFMIF-DONES for Radioisotope production An alternative of235U fission method is to irradiate directly Molybdenum to produce99Mo. It is produced by two ways the98Mo(n, )99Mo and100Mo(n,2n)99Mo reactions. However the100Mo(n,2n)99Mo cross section has a threshold energy at about 7 MeV then this way of production is not reached by conventional reactors. Neutron Energy of Fission below 7 MeV Ratio Ratio DONES neutron source up to 55 MeV 1.17 % 1.17 % 98Mo(n, )99Mo 98Mo(n, )99Mo 98.83 % 98.83 % 100Mo(n, 2n)99Mo 100Mo(n, 2n)99Mo Taking into account that only there is a 9.82 % of 100Mo in a natural composition, higher amount of 99Mo could be obtained enriching the Molybdenum in 100M. in 100M. Taking into account that only there is a 9.82 % of 100Mo in a natural composition, higher amount of 99Mo could be obtained enriching the Molybdenum
Index 1. Why use IFMIF-DONES for Radioisotope production 2. Assessment of the 99Mo production in IFMIF-DONES 3. High level requirements of the RadioIsotope Production Device (RIPD) 4. Proposals of concepts design for the RIPD 99Mo assessment production considering the first RIPD mockups 5. 6. Radioisotope production device vs Neutron Spectral Shifter 7. Conclusions and Future works
Assessment of the 99Mo production in IFMIF-DONES Irradiation time determination of the molybdenum samples of MoO3 After 6 days of irradiation the sample is extracted from the TC to be purified and then transported outer the IFMIF-DONES installation installation After 6 days of irradiation the sample is extracted from the TC to be purified and then transported outer the IFMIF-DONES
Assessment of the 99Mo production in IFMIF-DONES Assessment for 99Mo production in the TC area The 100Mo(n,2n) and 98Mo(n, ) reaction have been taken into account for the 99Mo production 6 irradiation day Specific Activity (GBq/g Mo) Behind of HFTM The 100Mo(n,2n) and 98Mo(n, ) reaction have been taken into account for the 99Mo production 6 irradiation day Behind of HFTM Just in front of Duct Just in front of Duct Activity (GBq/g Mo) 51 2.24 2.24 51 The (n, ) process produces 99Mo of relatively low specific activity, from a low of 3.7 GBq/g to a high of 74 GBq/g depending on the neutron flux available in the reactor . GBq/g depending on the neutron flux available in the reactor . The (n, ) process produces 99Mo of relatively low specific activity, from a low of 3.7 GBq/g to a high of 74
Assessment of the 99Mo production in IFMIF-DONES Sensitivity analysis of the 99Mo production behind of HFTM Mesh used for Neutron spectra calculation 20 cm ~8 cm Considering an average production of 44 GBq/g in the Mesh and taking into account a density of 3.17 g/cm3of Mo in 4.69 g/cm3of100MoO3 and mesh volume of 100 cm3, the total activity reached of99Mo would be about 14 TBq after 6 days of irradiation. It would supply99Mo generators to cover the demand of Andaluc a (100 GBq per99mTc generator)
High level requirements of the RadioIsotope Production Device (RIPD) 1. Do not disturb the normal operation of the IFMIF-DONES. 2. The targets should be introduced and extracted in periods of 6-day without opening the TC 3. Automatic insertion and extraction of targets mechanical or pneumatic extraction and insertion Lateral or vertical access 6. To keep the integrity of the TC shielding 7. The target has to be solid or encapsulated to avoid contamination 7. Maximization of the irradiation volume to maximize the production rate. 8. The handling of the targets has to be done remotely. 9. The system must be cooled to maintain a constant temperature during irradiation. 10. Having an Hot Cell for handling irradiated targets. 11. To define specific safety protocols to insertion, extraction, purification and introduction in generators to be exported to Hospitals and research centers.
Index 1. Why use IFMIF-DONES for Radioisotope production 2. Assessment of the 99Mo production in IFMIF-DONES 3. High level requirements of the RadioIsotope Production Device (RIPD) 4. Proposals of concepts design for the RIPD 99Mo assessment production considering the first RIPD mockups 5. 6. Radioisotope production device vs Neutron Spectral Shifter 7. Conclusions and Future works
Proposals of concepts design for the RIPD R158 Proposals of EAI (to meet with the high level requirements) PROPOSAL 1: lateral mechanical sample insertion device for Radioisotope production Based on the Japanese proposal (O. Nasayiuki, FED 2021)) Transverse duct for sample Shielding plug during irradiation The dimensions of each plate is 0.9x27.5x11.4 cm3. (V=282.15 cm3) =28.5 cm =20 cm 100Mo sample holder Shielding plug during samples extraction The sealing of the inner of the TC is kept The dimensions of each plate is 0.9x27.5x11.4 cm3. (V=282.15 cm3)
Proposals of concepts design for the RIPD PROPOSAL 2: lateral sample insertion using a Rabbit system Transverse duct for sample Inside the duct there are several smaller ducts to transport the spherical specimens. Inner diameter of the duct could be 13 mm Spherical specimens of 10.5 mm diameter Transference table
Index 1. Why use IFMIF-DONES for Radioisotope production 2. Assessment of the 99Mo production in IFMIF-DONES 3. High level requirements of the RadioIsotope Production Device (RIPD) 4. Proposals of concepts design for the RIPD 99Mo assessment production considering the first RIPD mockups 5. 6. Radioisotope production device vs Neutron Spectral Shifter 7. Conclusions and Future works
99Mo assessment production considering the first RIPD mockups Neutron transport calculations performed to determine the 99Mo production rate considering proposal 1 Shielding D+ The length from HFTM to the Radioisotope Production Device is 1.3 cm D+ The length from HFTM to the first 100MO3plate is 8 cm The distance between 100MoO3plates is 1.1 cm The dimensions of each plate is 0.9x27.5x11.4 cm3. (V=282.15 cm3)
99Mo assessment production considering the first RIPD mockups Under these conditions, it is possible to produce ~ 69.80 TBq de 99Mo/99mTc, per week 1 2 3 4 Considering that one 99mTc generation has about an activity of 46 GBq, which could be equivalent to considering a 100 GBq just before taking out the sample. It means that we could obtain about 700 generators per week Taking into account that a hospital could need 2 generators per week, we could supply to 350 hospitals. 99Mo activity obtained in each plate after 6 days of irradiation using an average neutron fluence rate in each plate. ENRICHED MoO3 (95% 100Mo) Plate 1 Plate 2 Plate 3 Plate 4 TOTAL SPECIFIC ACTIVITY GBq/g 100Mo ACTIVITY (TBq) 24.14 20.85 17.81 15.24 21.59 18.65 15.93 13.63 69.80
Index 1. Why use IFMIF-DONES for Radioisotope production 2. Assessment of the 99Mo production in IFMIF-DONES 3. High level requirements of the RadioIsotope Production Device (RIPD) 4. Proposals of concepts design for the RIPD 99Mo assessment production considering the first RIPD mockups 5. 6. Radioisotope production device vs Neutron Spectral Shifter 7. Conclusions and Future works
Radioisotope production device vs Neutron Spectral Shifter The Radioisotope production device could have a similar effect like the Neutron Spectral shifter module (NSS) due to the 100Mo(n,2n)99Mo reaction D+
Index 1. Why use IFMIF-DONES for Radioisotope production 2. Assessment of the 99Mo production in IFMIF-DONES 3. High level requirements of the RadioIsotope Production Device (RIPD) 4. Proposals of concepts design for the RIPD 99Mo assessment production considering the first RIPD mockups 5. 6. Radioisotope production device vs Neutron Spectral Shifter 7. Conclusions and Future works
Conclusions and Future works A99Mo production assessment has been performed in IFMIF-DONES TC taking in advance the neutrons that cross the HFTM. Two mock-ups for the Radioisotope production devices have been proposed. Considering the mechanical insertion proposal conditions, it would be possible to cover the necessities of 350 hospitals of ~99Mo/99mTc per week. Then, the benefit of radioisotope production in IFMIF-DONES has been demonstrated starting from the assessment production of one of the most demanding radioisotopes for cancer diagnostics. This could mean a great social benefit since the demand of a large number of inhabitants could be covered and a great benefit for IFMIF-DONES project, on the one hand for its social impact and on the other because it could mean important funding for IFMIF-DONES operation. The works are ongoing to validate the different RIPD concepts proposed respect to the productions rates, radiation hazards, safety issues and design analysis.
