Radioisotopes in Diagnostics and Therapy Ulli Kster, Jean-Franois - - PowerPoint PPT Presentation
Radioisotopes in Diagnostics and Therapy Ulli Kster, Jean-Franois - - PowerPoint PPT Presentation
Summary of Session 2: Radioisotopes in Diagnostics and Therapy Ulli
- M. de Jong, O. Ratib, D. Thers, S. Ziegler
Don’t forget the fuel!
Radioisotopes: the “fuel” for nuclear medicine
- 1. What is the optimum fuel for an application ?
- 2. Are we using today the optimum fuel ?
- 3. Is there sufficient supply of fuel
at reasonable cost?
- 4. How reliable is the fuel supply ?
The quest for the optimum isotope
N Z
Over 3000 radioisotopes known:
- half-life
- decay properties
- chemical properties
PET isotopes
Radio- nuclide Half- life (h) Branching ratio + (%) E mean (MeV) Range (mm) F-18 1.83 96.7 0.25 0.7 C-11 0.34 99.8 0.39 1.3 N-13 0.17 99.8 0.49 1.8 O-15 0.03 99.9 0.74 3.2 Ga-68 1.13 89.1 0.83 3.8 Rb-82 0.02 95.4 3.38 20 Sc-44 3.97 94.3 0.63 2.5
PET isotopes
Radio- nuclide Half- life (h) Branching ratio + (%) E mean (MeV) Range (mm) F-18 1.83 96.7 0.25 0.7 C-11 0.34 99.8 0.39 1.3 N-13 0.17 99.8 0.49 1.8 O-15 0.03 99.9 0.74 3.2 Ga-68 1.13 89.1 0.83 3.8 Rb-82 0.02 95.4 3.38 20 Sc-44 3.97 94.3 0.63 2.5
Diagnostic Accuracy: PET vs SPECT
Bateman et al, J Nucl Cardiol 2006 Bateman et al, J Nucl Cardiol 2006
81 66 76 86 100 91 20 40 60 80 100 Sensitivity Specificity Accuracy SPECT PET
* * *p<0.001
p<0.001
%
#64: D. Le Guludec
PET isotopes
Radio- nuclide Half- life (h) Branching ratio + (%) E mean (MeV) Range (mm) F-18 1.83 96.7 0.25 0.7 C-11 0.34 99.8 0.39 1.3 N-13 0.17 99.8 0.49 1.8 O-15 0.03 99.9 0.74 3.2 Ga-68 1.13 89.1 0.83 3.8 Rb-82 0.02 95.4 3.38 20 Sc-44 3.97 94.3 0.63 2.5
Mother isotope: 271 d 25 d 60 y
Transport of short Transport of short-
- lived radioisotopes
lived radioisotopes
Small cyclotrons
#340: D. Lewis
Longer-lived PET isotopes
Radio- nuclide Half- life (h) Branching ratio + (%) E mean (MeV) Range (mm) Sc-44 3.97 94.3 0.63 2.5 Cu-64 12.7 17.6 0.28 0.8 Y-86 14.7 31.9 0.66 2.6 Zr-89 78.4 22.7 0.40 1.4 I-124 100.2 22.8 0.82 3.8 Tb-152 17.5 17 1.08 5
Nanoparticle PET-CT Imaging of Macrophages in Inflammatory Atherosclerosis
Nahrendorf M et al, Circulation 2008, 117(3) 379-387
64Cu-TNP
#64: D. Le Guludec
Longer-lived PET isotopes
Radio- nuclide Half- life (h) Branching ratio + (%) Branching ratio (%) h10 (mSv/h/GBq) Sc-44 3.97 94.3 101 0.324 Cu-64 12.7 17.6 0.5 0.03 Y-86 14.7 31.9 320 0.515 Zr-89 78.4 22.7 100 0.182 I-124 100.2 22.8 99 0.17 Tb-152 17.5 17 142
Longer-lived PET isotopes
Radio- nuclide Half- life (h) Branching ratio + (%) Branching ratio (%) h10 (mSv/h/GBq) Sc-44 3.97 94.3 101 0.324 Cu-64 12.7 17.6 0.5 0.03 Y-86 14.7 31.9 320 0.515 Zr-89 78.4 22.7 100 0.182 I-124 100.2 22.8 99 0.17 Tb-152 17.5 17 142
44Sc production: #275 F. Haddad, #268 M. Bunka, #276 E. Garrido
Scandium-44: image reconstruction
F-18 AC Sc-44 NAC
Sc-44 AC/BG-SUB 0.9 Sc-44 AC/BG-SUB 1.3
Sc-44 NAC Sc-44 BG-SUB
T air W
Sc-44 AC/BG-SUB 0.5 Sc-44 AC/BG-SUB 1.7
#339: M. Miederer
3-photon-cameras
#168: D. Thers
20 10 x106
x [mm]
0.2 0.4 0.6
- 0.2
- 0.4
- 0.6
30
0.4 0.2
- 0.2
- 0.4
- 0.6
0.6
z [mm]
#82: C. Lang
Applications:
34mCl 44Sc 52mMn 86Y 94(m)Tc 124I 152Tb
SPECT isotopes
Radio- nuclide Half-life (h) Eγ γ γ γ (keV) Branching ratio γ γ γ γ (%) Decay type Ga-67 78 93 42 EC Kr-81m 0.004 190 64 IT Tc-99m 6 141 89 IT In-111 67 171 245 90 94 EC I-123 13 159 83 EC Xe-133 126 81 38 β- Tl-201 73 69-82 59 EC Lu-177 161 113 208 6.2 10.4 β β β β- Additional SPECT tracers needed for preclinical studies and for tracing specific elements (e.g. 155Tb, 195mPt).
Imaging Studies Using PET and SPECT
KB Tumor-Bearing Nude Mice
152Tb-folate: 9 MBq
Scan Start: 24 h p.i. Scan Time: 4 h
155Tb-folate: 4 MBq
Scan Start: 24 h p.i. Scan Time: 1 h
161Tb-folate: 30 MBq
Scan Start: 24 h p.i. Scan Time: 20 min
PET SPECT SPECT #177: C. Müller
Immunology approach
Roelf Valkema, EANM-2008. Target (antigen) Antibody
Targeted radionuclide therapy
Roelf Valkema, EANM-2008.
Immunology Structural biology Coordination chemistry Nuclear physics and radiochemistry
Target Receptor Radionuclide Linker Peptide, antibody, etc.
- M. Zalutsky
- M. Zalutsky
Potential therapy isotopes ?
“In-cell heavy ion accelerator”: 2 fission products per decay 2 x 100 MeV deposited over 25 µ µ µ µm LET 4000 keV/µ µ µ µm on average 38 keV average beta energy plus 1.6/decay conv. elect. 28-53 keV plus many Auger electrons <7 keV 33/decay Auger electrons
M.T. Azure et al., AAPM Symp. 8 (1992) 336. J.D. Willins, G. Sgouros, JNM 36 (1995) 315. production: #207 M.M. Günther, #319 U. Köster
Some interesting isotopes just cannot be produced well.
- M. Zalutsky
- M. Zalutsky
More on alpha therapy: #301 F. Davodeau #294 I. Kelson
Targeted Alpha Radionuclide Therapy
KB Tumor-Bearing Mice Treated with 149Tb-Folate
A: control B: treated
32 d < 56 d
control
149Tb-folate
X X
- therapy
α
#177: C. Müller
Folic acid
Targeted Beta Radionuclide Therapy
KB Tumor-Bearing Mice Treated with 161Tb-Folate
C: control D: treated
28 d < ? d
- therapy
control
161Tb-folate
X X X X
β
#177: C. Müller
Radionuclides for RIT and PRRT
Radio- nuclide Half- life E mean (keV) E (B.R.) (keV) Range
Y-90
64 h 934
- 12 mm
I-131
8 days 182 364 (82%)
3 mm Lu-177
7 days 134 208 (10%) 113 (6%)
2 mm Tb-161
7 days 154 5, 17, 40 e- 75 (10%)
2 mm 1-30 m Tb-149
4.1 h 3967 165,..
25 m Ge-71
11 days 8 e-
- 1.7 m
Er-165
10.3 h 5.3 e-
- 0.6 m
localized cross-fire Modern, better targeted bioconjugates require shorter-range radiation need for adequate (R&D) radioisotope supply.
Estab- lished isotopes Emerging isotopes R&D isotopes: supply- limited!
LET of Auger electrons
A.I. Kassis, Rad. Prot. Dosimetry 143 (2011) 241.
Micro-Injections of 71Ge
Injected volume is 0.05 to 0.3 pL #338: M. Jensen
Nucleus and cytoplasm
Injected volume monitored by Quantum Dots (red) #338: M. Jensen
Radioisotopes: the “fuel” for nuclear medicine
- 1. What is the optimum fuel for an application ?
- 2. Are we using today the optimum fuel ?
- 3. Is there sufficient supply of fuel
at reasonable cost?
- 4. How reliable is the fuel supply ?
The traditional supply chain of 99Mo/99mTc
L'OCDE s'inquiète des risques de pénurie d'isotopes médicaux
53% demand 23% demand 20% demand
Back to the roots ? Original discovery of Tc in cyclotron-irradiated Mo !
- C. Perrier, E. Segrè, J. Chem. Phys. 5 (1937) 712.
Sourcing of enriched 98Mo
Non-fission production of 99Mo needs often large quantities of enriched Mo (1 kg 98Mo vs. 4 g 235U). boiling point: UF6 56 ° ° ° °C MoF6 34 ° ° ° °C Cost of enriched 98Mo or 100Mo: few hundred USD per gram for large quantities (kg). Joint production of 98Mo and 100Mo more cost-effective.
Other suppliers?
Natanz, Iran
The producing reactor gets only 0.26 EUR per 99mTc patient dose, similar to the price of a single cheap pill.
Evolution of 82Sr demand in the USA
(source : Department
- f Energy, USA)
82Rb is used for PET in cardiology
82Sr/82Rb generator Le Guludec (Paris) - PET-CT in cardio-vascular diseases #275: F. Haddad
Facilities producing Sr-82 in the world
- LANL, USA –100 MeV, 200µA
- BNL, USA –200 MeV, 100µA
- INR, Russia –160 MeV, 120µA
- iThemba, South Africa –66 MeV, 250µA
- TRIUMF, Canada –110 MeV, 70 µA
BLIP
5 accelerators – 2 generator manufacturers – 1 generator Mar - Jul 2011:
- utage of 2 accelerators > 82Sr shortage
Jul ‘11-Feb ‘12: generator recalled
#275: F. Haddad
Problem: Concentration on few players
New players
#275: F. Haddad
Upcoming: 70 MeV cyclotron in Legnaro Two new 82Sr/82Rb generators (Draximage, Quanticardi)
R&D isotopes
149Tb-therapy 152Tb-PET 155Tb-SPECT 161Tb-therapy
& SPECT #177: C. Müller
#146: T. Stora
#146: T. Stora
#220: D. Pauwels
Also possible at: TRIUMF, PSI, ISIS, SNS, LANL, J-PARC, ESS, EURISOL,…
Irradiation Cooling Dissolution Filtering Iodine removal Acidifying
99Mo
separation
99Mo
purification QC, calibration, distribution Intermediate (ILW) and low level liquid waste (LLW) Off-gas treatment Xenon decay Ventilation Precipitate (U, TU, RE, EA, Te, Zr, Nb, etc.) High level solid waste
Extraction of fission-moly
133Xe 131I
Supply issues ?
1.
131I is coproduced with 99Mo by 235U fission
about 1000 kCi 131I producible per year corresponding to about 5 million doses (100 mCi) exceeds demand by far [additional dedicated production via 130Te(n, 131I]
Fission waste recycling with the Purex process
Supply issues ?
1.
131I is coproduced with 99Mo by 235U fission
about 1000 kCi 131I producible per year corresponding to about 5 million doses (100 mCi) exceeds demand by far [additional dedicated production via 130Te(n, 131I] 2.
90Y is obtained from 90Sr/90Y generators
EDF reactors produce 1.4 tons of 90Sr per year corresponding to 200 MCi 90Sr from these 10 GCi of 90Y can be eluted per year, enough to supply one 90Y dose (100 mCi) per year for every human!
1990 1995 2000 2005 2010 10 20 30 40 50
90Y 177Lu
Pub Med Therapeutic Studies
Year
177Lu low energy beta-emitter for therapy
moderate β--energy
- low
side effects
- safe handling
imageable γ-rays
- dosimetry
- therapy control
Lu 177
6.647d β β β β - 160.1 d β β β β -
Hf 177 18.60
#270: K. Zhernosekov
The rising star for therapy
Lu 176 2.59
3 + 2070
Lu 175 97.41
8
Yb 176 12.7
3
Lu 177
6.647d β β β β -
Yb 177 1.9 h
β
160.1 d β β β β -
Yb 175 4.2 d
β
Yb 174 31.8
68
Hf 177 18.60 Hf 176 5.206
specific activity 20 – 30 Ci/mg (vs. theoretical 110 Ci/mg)
- nly 25 % of hot 177Lu atoms
75% of cold 175/176Lu atoms
176Lu(n,γ)177Lu
“Carrier-added” c.a. 177Lu
long-lived radioactive impurities: ∼0.01 % of 177mLu waste management; environment exposure #270: K. Zhernosekov
Lu 176 2.59
3 + 2070
Lu 175 97.41
8
Yb 176 12.7
3
Lu 177
6.647d β β β β -
Yb 177 1.9 h
β
160.1 d β β β β -
Yb 175 4.2 d
β
Yb 174 31.8
68
Hf 177 18.60 Hf 176 5.206
176Yb(n,γ)177Yb 177Lu
“No -carrier-added” n.c.a. 177Lu
highest specific activity > 100 Ci/mg (vs. theoretical 110 Ci/mg) and highest radionuclide purity Yb-target must be quantitatively removed by chemical separtion #270: K. Zhernosekov
2 4 6 8 10 12 14 25 50 75 100 25 50 75 100
Sth = 110 Ci/mg S1/2 = 92 Ci/mg S
1/2 = 16 Ci/mg
Specific Activity [Ci/mg] Days
Shelf-life/ c.a. vs n.c.a. 177Lu
#270: K. Zhernosekov
Physical quantity describing the activity per mass (GBq/mg, Ci/mg), basically the ratio of radioactive atoms to all atoms (including stable ones).
Specific activity
Carrier added vs. non-carrier added
ca
nca
Saturation of selective receptors per cell
SPECT/CT day 1 p.t. Lu-octreotate
NCA 177Lu-octreotate, 2 µg
- Conv. 177Lu-octreotate, 11 µg
adrenals adrenals tumour tumour
- M. de Jong
Tumour uptake, based on SPECT quantification
Clearance rate was similar: 67
- 10 vs. 72
- 12 h
NCA 177Lu-octreotate: ~2x higher tumour uptake 70 vs. 35 Gy tumour dose
- M. de Jong
Pumping: power 120 – 130W, = 510nm, f = 10kHz, = 20ns.
Output of the system: 3 g/ year Final isotope content:
- Yb – 168 – 20.21% (only 0.14 % in natural
Yb)
- Yb – 170 – 2.36%
- Yb – 171 – 18.38%
- Yb – 172 – 15.45%
- Yb – 173 – 12.1%
- Yb – 175 – 22.38%
- Yb – 176 – 9.12%
Channel Wavelength, nm Dye Power, W Spectr.band, MHz Pulse width, ns 1 555 R110 5 500 15 2 581 R6G 5 500 15 3 582 R6G 20 3104 20
Parameters of 3 Parameters of 3-
- Channel Dye
Channel Dye -
- Laser System
Laser System for AVLIS of Ytterbium for AVLIS of Ytterbium #157: S. Akulinichev
The history of lutetium separation
1878 Separation of Yb in Geneva by Jean-Charles Galissard de Marignac 1907 Separation of Lu from Yb Georges Urbain Carl Auer von Welsbach Charles James 1995- Large-scale separation of Lu for production of LSO crystals by Mark Andreaco (CTI) and George Schweitzer (Univ. Tennessee) 2007 Rapid large-scale separation
- f n.c.a. 177Lu from irradiated Yb
by ITG Garching
Outlook
The ideal agent for cancer therapy would consist of heavy elements capable of emitting radiations of molecular dimensions, which could be administered to the organism and selectively fixed in the protoplasm of cells one seeks to destroy. While this is perhaps not impossible to achieve, the attempts so far have been unsuccessful.
- C. Regaud, A. Lacassagne, Radiophysiologie et Radiotherapie 1 (1927) 95.