5 th international conference on isotopes brussels, belgium, 25 – 29 april 2005

5th International Conference on Isotopes

Brussels, Belgium, 25 – 29 April 2005

Enzo Menapace

ENEA, Advanced Physical Technologies, Bologna, Italy

Claudio Birattari, Mauro L. Bonardi, Flavia Groppi

Anna Martinotti, Sabrina Morzenti, Cristiano Zona

Radiochemistry Laboratory, LASA,

Universita’ degli Studi and INFN, Milano, Italy

e-mail: [email protected]

RECENT ACTIVITIES ON INNOVATIVE RADIONUCLIDE RECENT ACTIVITIES ON INNOVATIVE RADIONUCLIDE PRODUCTION FOR METABOLIC RADIOTHERAPY AND PET AND PRODUCTION FOR METABOLIC RADIOTHERAPY AND PET AND

ON RELEVANT EXPERIMENTAL AND EVALUATED NUCLEAR ON RELEVANT EXPERIMENTAL AND EVALUATED NUCLEAR DATADATA

25 - 29 April 2005 5ICI, Brussels, Belgium 2

Activities and relevant results are discussed concerning the radionuclide production for medical applications brought up in the recent years at LASA-INFN Laboratory in collaboration with ENEA, Division for Advanced Physical Technologies. In particular, measurements are discussed concerning spectrometric values with reference to radionuclidic, radiochemical and chemical purities by analytical and radioanalytical techniques.

Concerning the excitation functions, relevant to the nuclear reactions involved in the radionuclide production, evaluated nuclear data are discussed as they have been produced through appropriate comparisons of present and other available and critically selected experimental values with reliable model calculations.

Most significant results are presented as from recent years activities at the above Institutes.

AbstractAbstract


IntroductionIntroduction

A number of initiatives on the production of innovative medical radioisotopes, both for PET and SPECT diagnostics and for therapy, have been brought up in the recent years by the present authors at INFN-LASA Laboratory and ENEA, Division for Advanced Physical Technologies, by collaborations with the Cyclotron Laboratory of JRC-Ispra (EC) referring to irradiation experiments at K=38 variable energy Cyclotron.

Mainly scientific aspects and applications have been investigated in order to obtain high specific activity accelerator-produced radionuclides in no-carrier-added (NCA) form.

To this aim it was necessary to optimise the irradiation parameters, determining the excitation functions of the involved nuclear reactions, and to point out selective radiochemical separations of the radioisotopes of interest.


Relevant examples of medical High Specific Activity RadioNuclides – HSARN previously produced in NCA form, at Milano and Ispra Cyclotron Laboratories

TargetNuclear

ReactionsRadioNuclide

producedEnergy Range

MeVSA (CF)GBq/g

Exp. IDF°

Sc-45 (p,n) Ti-45 15 - 9 837 nd

V-nat (p,xn) Cr-51 15 - 8 3 46

Zn-nat (p,xn) Ga-66,67 29 - 15 187; 22 37; 13

Ge-nat (p,xn) As-72,74 16 - 4 62; 3.7 10; 5

As-75 (pxn) Se-73,75 32 - 17 224; 0.5 10 - 30

Kr-nat (p,xn) Rb-81 Kr-81m 40 - 30 313 nd

Mo-nat (p,xn) Tc-94g, 95m,g, 96g 40 - 20 131; 0.8; 61; 12 10 - 50

Cd-nat (p,xn) In-111,114m 27 - 15 15; 0.9 3; 10

Te-nat (p,xn) I-123,124 28 - 17 71; 9 20

Te-124 (p,2n) I-123 28 - 17 71 10

Os-nat (,xn) Pt-191 36 - 24 9 48

Ir-nat (p,xn) Pt-191 36 - 17 9 NCF

Au-197 (p,3n) Hg-195m,g Au-195m 33 - 18 15; 63 30

Hg-nat (p,xn) Tl-201 25 - 15 8 5

Hg-202 (p,2n) Tl-201 19 - 10 8 5

Tl-203 (p,3n) Pb-201 Tl-201 27 - 19 8 10


IntroductionIntroduction

Measurements of spectrometric values and of radionuclidic, radiochemical and chemical purities, by analytical and radioanalytical techniques, have been done at LASA-INFN, as pointed out in the following.

Evaluated nuclear data have been produced at ENEA, Division for Advanced Physical Technologies through appropriate comparisons of presently investigated and critically selected experimental values with reliable model calculations, as discussed in the following.

Participation is done to international co-operation initiatives, especially to the IAEA Coordinated Research Programmes (CRPs) on nuclear data for production of medical radioisotopes.

In the recent years up to the present, the R&D activity (as from ref.s /1/ to /6/) has been brought up or it is underway for the following NCA radionuclides, for uses in metabolic radiotherapy and PET:


Investigated medical radioisotopes, production reactions, emitted radiation data and applications

Radionuclide T1/2 reactions gamma emissions imaging radiotherapy

64Cu 12.70 h natZn (d,X) 511 keV PET + and -

61Cu 3.33 h natZn (d,X) 511 keV PET impurity

66Ga 9.49 h natZn (d,xn) 511 keV

many gammasPET

-camera+ , 4.2 MeV

186gRe 89.25 h 186W (p,n) 186W (d,2n)

137 keVother gammas

SPET

-camera- , 1.1 MeV

211At 211Po

7.22 h

516 ms209Bi (,2n) X 79 keV -camera

, 5.868 MeV , 7.448 MeV

210At 210Po

8.3 h

138.4 d209Bi (,3n) many gammas -camera

internal spike

, 5.304 MeV

225Ac 213Bi 213Po

10.0 d

45.6 m

4.2 s

226Ra (p,2n) many gammasSPET

-camera

, 5.829 MeV, others

- , 1.4 MeV

, 8.375 MeV

103Pd 16.97 d 103Rh (d,2n)X 20,22,23 keV

some gammas- - - X 20, 22, 23 keV


Materials and experimental methodsMaterials and experimental methods The irradiations were carried out at the Scanditronix MC40 cyclotron (K=38),

JRC-Ispra (Varese, Italy) of the EC, that can deliver variable energy proton or alpha beams with energies up to 38 MeV and deuteron beams up to 19 MeV.

The experimental activity devoted to the At radionuclides (RNs) is discussed here as a significant example. 211At is clearly the most promising for labelling drugs and radiopharmaceutical compounds for metabolic radionuclide therapy, as:

the half-life of 7.214 h, reasonably sufficient long for labelling organic compounds, due to the strengths of C-At, O-At and N-At bonds, which are similar to those of iodine;

the 211At branching of 41.80%, which is the highest among the “medium-lived” At RNs.

Although decaying by EC, the further 58.20% also leads to emission through 211gPo.

As a consequence the “overall” branching of the decay of 211At is 100%.

The energy of particles ranges from 5 870 keV to 7 450 keV (with a raw arithmetically “averaged“ value of 6 665 MeV).


Materials and experimental methodsMaterials and experimental methods

The two main particles of the 211At 211gPo system have an “average” range of 60 to 67 m in water (and soft animal tissues) and a nearly optimal LET of 100 - 130 eV·nm-1, which is around the maximum of the Q curve

for energetic ions. A good choice for a production method of 211At has to minimize isotopic

contamination by the Po isotopes to negligible levels.

The direct production method based on the nuclear reactions 209Bi(,2n)211At seems the most satisfactory, because it can be done in a medium energy cyclotron, leading to a high yield and low contamination by the only radioisotopic impurity 210At, that can be kept at an appropriate level as internal spike.

The irradiation experiments were carried out at low beam current (50 to 250 nA), with an integrated beam charge of 100 and 450 C, measured with an error smaller than 1-2% with a Faraday cup connected to a charge integrator. Besides, the reliability of beam charge integrator was checked by thin Cu monitor foils.


Materials and experimental methodsMaterials and experimental methods

In order to produce NCA 211At/211gPo for metabolic radiotherapy, a suitable radiochemical separation of At radioisotopes from Po by-products and from the Bi target with quality control has been done, the radiochemical separation adopted being a classical “wet” method based on liquid/liquid extraction.

The , X spectra have been measured with coaxial HPGe detectors, the spectra with Si surface barrier or PIPS detectors, with a resolution of 27 keV (FWHM), and spectra with a conventional liquid scintillation counting LSC and spectrometry system with / pulse shape analysis (PSA) discriminator. Significant results are presented in the next figures.

The radionuclidic purity of the different radiochemistry fractions produced from Bi

target, 210Po impurities and the final solution were also determined accordingly.


500 1000 1500 2000101

102

103

104

105

106

107

207Bi1770.23

207Bi1063.67

210At1181.4 1436.71483.6 1599.7

210At245.31

211At669.60 742.64

211At/211gPo897.80

211At687.00

211At/211gPo569.702

211At/211gPo328.12

cou

nts

gamma energy (keV)

HPGe spectrum – 28.8 MeV irradiation

50 60 70 80 90 100 110105

106

107

zoom region211At/211gPo

92.4 keV

89.6 keV

79.3 keV

76.9 keV

coun

ts

gamma energy (keV)


5000 6000 7000 80000

200

400

600

800

1000

1200

after L/L exstraction

7450

.6 k

eV

5867

.7 k

eV

5304

.4 k

eV

210 P

o (

t 1/2=

138

.376

d)

cou

nts

x c

han

nel

s-1

211g

Po

(t 1/

2= 5

16 m

sec)

211 A

t (t

1/2=

7.2

14 h

)

alpha energy (keV)

5000 6000 7000 80000

20

40

60

80

100

120

5304

.4 k

eV

kco

un

ts x

ch

ann

els-1

polonium fractionin aqueous phase

210 P

o (

t 1/2=

138

.376

d)

alpha energy (keV)

5000 6000 7000 80000

30

60

90

120

150

180

210

240

5867

.7 k

eV

7450

.6 k

eV

kco

un

ts x

ch

ann

els-1

astatine fractionin organic phase

211g

Po

(t 1/

2= 5

16 m

sec)

211 A

t (t

1/2=

7.2

14 h

)

alpha energy (keV)

alpha spectrum after the liquid/liquid extraction: the peaks of both 211At-211gPo and 210Po are shown together (related to 32.8 MeV irradiation).

alpha spectrum of the astatine fraction (extracted by the organic solvent): At product is completely extracted from the aqueous solution.

alpha spectrum of the separated 210Po fraction (remained in the aqueous phase): none of the 210Po is taken into the organic solvent extraction.


Nuclear models and computing codesNuclear models and computing codes

The role of the nuclear model calculations has been well recognised for the nuclear data evaluation activities in the NEA and IAEA context and a number of initiatives on the matter have been undertaken both for the validation of the computing codes with respect to measured values and for the model parameterisation and systematics aimed to reliable data calculations particularly in the case of scarce, lacking or discrepant measurements.

Calculations for the involved nuclear reactions have been carried out at ENEA Division for Advanced Physical Technologies, through internal developed codes and mainly through the EMPIRE-II system (be M. Herman, IAEA-NDS, ref./8/), accounting for the major nuclear reaction mechanisms for the various competing nuclear reaction channels, including the Optical Model (OM) and the full featured Hauser-Feshbach model, with a comprehensive parameter library mainly covering nuclear masses, OM data, discrete nuclear levels, level densities and decay schemes.

Particularly the Monte Carlo Pre-equilibrium approach for the investigated proton induced reactions has been successful in approximating experimental values.


As the determination of the nuclear level density is of the main impact on the results, the following semiempirical formula was adopted (Frisoni et al., 1997) founded on both theoretical and empirical (from the existing measurements) bases:

where:E is the nuclear excitation energy; is the parity; is the spin cutoff factor;

Nuclear models and computing codes (cont.)Nuclear models and computing codes (cont.)

),( )( 212

),,(2

2

24/54/1

])(2[

EFeEa

eME par

MEa

)1( )( EeaEa

2

2

1 ),(

EtghEFpar

M is the projection of the angular momentum on a given axis;Fpar takes into accont the level parity distribution.

The level density parameter (the most important one) and the other parameters (, and ) are estimated by best approximation of:

low energy level schemes; neutron resonance average spacings; emission spectra

with reference to the available experimental and theoretical informations.

a


Evaluations for the involved excitation functionsEvaluations for the involved excitation functions

The evaluations have been based both on selected experimental data and on nuclear model calculations. In particular, the activity has been devoted to the model parameterisation, especially concerning the nuclear discrete level structure and the level density approach in the continuum, for both target and residual nuclei.

The excitation functions were evaluated for the production reactions of radionuclides as from the above table scheme. Most recent evaluations concerned (,2n) and (,3n) reactions on 209Bi target for the production of 211At and 210At, and the radioisotope production reactions 186W(p,n)186gRe and 103Rh(d,2n)103Pd and 226Ra(p,2n)225Ac.

The research was especially aimed to investigate the production optimal conditions, relevant to future Cyclotron irradiations experiments by proton and deuteron beams.

A satisfactory agreement has been found between the theoretical results and the existing experimental values as shown in the figures reported in the following.


In this work, special care is devoted to the discussion of the results for the production of the:

211At, 210At, 186gRe and 103Pd radionuclides by the above reaction routes.

For the other radionuclides, the relevant results, as from ref.s /1/ , /2/, /3/, /4/ and /5/, are reviewed hereafter.


Relevant comments (I)Relevant comments (I)

The cumulative excitation functions are presented for the production of 64Cu and 66Ga by nuclear reactions on natural zinc target in the energy range up to 19 MeV, such as (d,xn) reactions for 64Cu, (d,2p) reaction for 64Cu production and (d,xn) reactions for 66Ga production;

the experimental values, obtained from the analyses of the above mentioned irradiation experiments, are consistently compared with the model calculations (full lines) for 64Cu and 66Ga production reactions in the incident energy intervals from the thresholds up to 19 MeV.


RadionuclideNuclear reaction

Eth

MeV

Cu-64

t½ = 12.701 h

66Zn(d,) 0

67Zn(d,n) 0

68Zn(d,2n) 10.3

64Zn(d,2p) 1.0

66Zn(d,2p2n) 20.6

67Zn(d,2p3n) 27.9

Cu-61

t½ = 3.33 h

64Zn(d,n) 1.4

66Zn(d,3n) 21.0

Ga-66

t½ = 9.49 h

66Zn(d,2n) 8.4

67Zn(d,3n) 15.7

68Zn(d,4n) 26.2

RadionuclideNuclear reaction

Eth

MeV

Ga-67

t½ = 3.26 d

66Zn(d,n) 0

67Zn(d,n) 4.1

68Zn(d,3n) 14.6

Zn-65

t½ = 244.26 d

64Zn(d,p) 0

66Zn(d,p2n) 13.2

67Zn(d,p3n) 20.4

68Zn(d,p4n) 30.9

Zn-69m

t½ = 13.76 h

68Zn(d,p) 0

70Zn(d,p2n) 11.7

ENERGY THRESHOLDS FOR THE MAIN NUCLEAR ENERGY THRESHOLDS FOR THE MAIN NUCLEAR REACTIONS INDUCED BY REACTIONS INDUCED BY DEUTERONDEUTERON BEAMS ON BEAMS ON ZINC ZINC

TARGET OF NATURAL ISOTOPIC COMPOSITIONTARGET OF NATURAL ISOTOPIC COMPOSITION

Natural Zn (%): 64Zn 48.6, 66Zn 26.9, 67Zn 4.1, 68Zn 18.8, 70Zn 0.6


COMPARISON BETWEEN EXPERIMENTAL AND COMPARISON BETWEEN EXPERIMENTAL AND CALCULATEDCALCULATED CROSS-SECTIONS CROSS-SECTIONS

2 4 6 8 10 12 14 16 18 20

1

10

100

64Cu - model calculation

66Ga - model calculation

cro

ss s

ecti

on

(cm

2 x10-2

7 )

deuteron energy (MeV)

66Ga - experimental values

64Cu - experimental values


0 200 400 600 800 1000 1200 1400 1600 1800 2000100

1000

10000

100000

1000000

ZoomRegion

Co-58impurity!

double escapeX-rays(Pb backscattering)plus Cu, Zn, Ni)

511 kev beta +

****

*

*

*

*

*

*

**

log

(co

un

ts)

gamma energy (keV)

1250 1275 1300 1325 1350 1375 14000

200

400

600

800

1000

Cu-64 1346 keVemission intensity 0.473 %

1357

13461333

Ga-66

Ga-6

6

Cu

-64

ZoomRegion

linea

r (c

ou

nts

)

gamma energy (keV)

HPGe SPECTRUMHPGe SPECTRUM OF A DEUTERON IRRADIATED OF A DEUTERON IRRADIATED ZINC ZINC TARGET TARGET

((Pb absorbersPb absorbers 3mm + 3mm + ++ annihilators annihilators 2x7 mm) 2x7 mm)

Cu-64 (Cu-61)Ga-66 Ga-67

Zn-65 Zn-69m


THIN-TARGETTHIN-TARGET YIELDS OF YIELDS OF CU-64CU-64 AND AND CU-61CU-61 vs. vs. ““AVERAGE” DEUTERON ENERGY IN THE THIN TARGETSAVERAGE” DEUTERON ENERGY IN THE THIN TARGETS

4 6 8 10 12 14 16 18 2010

100

1000

copper-61

copper-64t1/2

= 12.701 h

t1/2

= 3.33 h

experimental values 61Cu

analytical fitting 61Cu

experimental values 64Cu

analytical fitting 64CuTh

in T

arg

et Y

ield

(M

Bq

/C M

eV)

deuteron energy (MeV)


EXPERIMENTAL AND INTEGRATED THICK-TARGETEXPERIMENTAL AND INTEGRATED THICK-TARGET YIELD YIELD at the EOIBat the EOIB for Zn(d,X) nuclear reactions at 19 MeVfor Zn(d,X) nuclear reactions at 19 MeV

beam energy: 19 : 19 ± 0.2 ± 0.2 MeV; beam current: 100 nA; irradiation time: 30 MeV; beam current: 100 nA; irradiation time: 30 min; target thickness: 730 min; target thickness: 730 m (m (total energy absorption + 10 %total energy absorption + 10 %))

Radionuclide T1/2

gamma (keV)

Thick-Target Yield exp EOIB (MBq/C)

Error (1 SD)

(MBq/C)

Thick-Target Yield int EOIB

(MBq/C)

%

Exp-Int

64Cu 12.701 h 1345.84 8560 240 8447 1.33

61Cu 3.33 h 656.01 28887 1219 26486 8.31

66Ga 9.49 h

833.50

1039.35

1333.00

38441

(weighted average)

505 40376 5.03

67Ga 3.2612 d300.22

393.50

4523

(weighted average)

59 4578 1.20

65Zn 244.26 d 1115.55 132 87 131 0.57

69mZn 13.76 h 438.63 4031 90 4037 0.14

1 MBq.C1 MBq.C-1 -1 = = 3.6/37 3.6/37 Ci. Ci. AA-1-1.h.h-1-1


1 . irrad ia ted ta rg e td isso lutio n

2 . liq u id / liq u idex trac tio n

3 . an io n exch an g ech ro m ato g rap h y

e lu te C u (II)w ith 2 .0 M H C l

copper-64,61R C H Y > 9 0 % , R N P 9 9 .9 %

e lu te Z n (II)w ith 0 .1 M H C l

zinc-69m ,65R C Y > 9 5 %

w ash w ith 3 M H C le lu te sodium -24

fill Z n (II), C u (II) an d traces G a(III)on to A G 1 X 8 co lu m n

d ry an d red isso lvein 3 .0 M H C l

aq u eou s p h ase 7 M H C lz in c , cop p er

b ack -extrac tin 0 .0 1 M H C l

gallium -66,67R C Y 9 9 % , R N P 9 9 %

org an ic p h aseg a lliu m -6 6 ,6 7

extrac t (2 to 3 t im es )in iso -p rop h yle th er

d ry an d red isso lvein 7 .0 M H C l

Z n d isso lu tionin 7 .0 M H C l

Scheme of Radiochemistry and Q.C. for N.C.A. radio-Cu and radio-Ga separation from irradiated zinc target

• radionuclidic purity• radiochemical purity

• specific activity• chemical purity


Characteristics of Characteristics of 225225AcAc

TT1/2 1/2 = 10 d= 10 d

Generator of Generator of 203203Bi (TBi (T1/2 1/2 = 45 min)= 45 min)

203203Bi labeled tumor seeking compounds are already in clinical Bi labeled tumor seeking compounds are already in clinical experimentation (Phase I) for lymphoma therapyexperimentation (Phase I) for lymphoma therapy

Production of Production of 225225AcAc

Decay of Decay of 229229ThTh

Cyclotron activation via Cyclotron activation via 226226Ra(p,2n)Ra(p,2n)225225AcAc

Cyclotron used: FzK KarlsruheCyclotron used: FzK Karlsruhe


Relevant comments (II)Relevant comments (II)

For the 226Ra(p,2n) reaction cross section, the Institute for Transuranium Elements (ITU) of the JRC in collaboration with the cyclotron of the Forschungszentrum Karlsruhe, Germany, has demonstrated the feasibility of the production of 225Ac in a cyclotron based on the reaction 226Ra(p,2n)225Ac. The excitation function of this reaction was determined by irradiation of a series of identical Ra-targets containing 12.5 µg 226Ra.

The experimental cross section values presented at 2004 Cyclotron Conference in Tokio, as from ref. /9/, are shown in the next figure in comparison with model calculations using the EMPIRE-II code.

Those first published experimental values appear to be in good agreement with the model calculations. Maximum yields of 225Ac are shown at incident proton energies around 16.8 MeV.


10 20 30

0

100

200

300

400

500

600

700

800

Measurements - ref./9/ Model calculation

226Ra(p,2n)225Accro

ss

se

cti

on

(c

m2 x

10

-27 )

proton incident energy (MeV)

Production of Production of 225225Ac via (p,2n) reaction on Ac via (p,2n) reaction on 226226Ra targetRa target


Production of Production of 225225Ac via (p,2n) reaction on Ac via (p,2n) reaction on 226226Ra targetRa target

5 10 15 20 25 30 35

Exp.ALICEEMPIRE-II

0

100

200

300

400

500

600

700

800cr

oss

sect

ion

(m

b)

proton energy (MeV)

Ra-226 (p,2n) Ac-225


Relevant comments (III)Relevant comments (III)

For the excitation functions of the (p,n) reactions on 186W target for the production of 186gRe in the incident energy interval up to 20 MeV, the experimental values from the literature are compared with the theoretical ones (full lines) obtained through the EMPIRE-II code. Particularly the Monte Carlo Pre-equilibrium approach has been successful in approximating the experimental values;

the discussion on possible systematic errors appears to be desirable in order to solve the present experimental discrepancies;

this production method can provide NCA 186gRe as an alternative route to the CA production utilizing a reactor neutron field via (n,) reaction on enriched 185Re target.


Production of Production of 186186Re via (p,n) reaction on Re via (p,n) reaction on 186186W targetW target

10 20 30

0

20

40

60

80

100

120

140c

ros

s s

ec

tio

n (

cm

2 x 1

0-2

7 )

proton incident energy (MeV)

Szelecsenyi et al. (1997) Shigeta et al.(1996) Zhang et al (1999) Model calculation


Relevant comments (IV)Relevant comments (IV)

Concerning the 103Rh(d,2n)103Pd reaction route for producing an highly relevant radioisotope for local therapy treatments, two data sets from one experimental work have been considered, concerning respectively:

- detected X-rays in the energy interval from 5 to 20.2 MeV;

- detected week gamma-rays in the energy interval from 8.7 to 20.2

MeV.

In the following figure the comparison of theoretical model calculations with the experimental values shows a satisfactory agreement, taking into account the experimental uncertainties.


Production of Production of 103103Pd via (d,2n) reaction on Pd via (d,2n) reaction on 103103Rh targetRh target

5 10 15 20

0

500

1000

1500

cro

ss s

ecti

on

(cm

2 x 1

0-27 )

deuteron incident energy (MeV)

Hermanne A., et al, (2002) - X line Hermanne A., et al. (2002) - gamma line Model calculation


Relevant comments (V)Relevant comments (V)

Experimental cross section data have been selected for (,2n) and (,3n) reactions on 209Bi target for the production of 211At and 210At respectively, in the incident energy interval from 20 MeV to 50 MeV;

those experimental values are compared with model calculations ones (full line) obtained utilising the EMPIRE-II code;

the thick target yield value obtained by integration of the theoretical curve, from 28.8 down to 20 MeV, is 9234 MBq·C-1, in comparison with the experimental value equal to 8085 ± 176 MBq·C-1 for the total energy absorption, as obtained at LASA-INFN from a preliminary irradiation: the discrepancy of about 12.4% appears to be reasonable with regard to the present experimental conditions.


Production of Production of 211211At via (At via (,2n) reaction on ,2n) reaction on 209209Bi targetBi target

20 25 30 35 40 45 50

0

200

400

600

800

1000

1200

209Bi(,2n)211At

alpha incident energy (MeV)

cro

ss s

ecti

on

(cm

2 x 1

0-27 )

E.L. Kelly and E. Segrè - 1949(I) E.L Kelly and E. Segrè - 1949 (II) E.L. Kelly and E. Segrè - 1949 (III) W.J. Ramler et al. - 1959 R.M. Lambrecht et al. - 1985 A. Hermanne et al. - ARI 2004, in press /7/ Model calculation


Production of Production of 210210At via (At via (,3n) reaction on ,3n) reaction on 209209Bi targetBi target

30 35 40 45 50 55 60 65 70-200

0

200

400

600

800

1000

1200

1400

1600

cro

ss s

ecti

on

(cm

2 x 1

0-27 )

209Bi(,3n)210At

alpha incident energy (MeV)

Kelly-Segrè 1949 (I) Kelly-Segrè 1949 (II) Kelly-Segrè 1949 (III) Ramler 1959 Stickler et al. 1974 Lambrecht-Mirzadeh 1985 Rattan et al. 1986 Rizvi-Bhardway 1990 Singh-Mukherjee 1994 Patel-Shah-Singh 1999 Hermanne et al. ARI-2004 in press /7/ Model calcutation


1. C. Birattari, M. L. Bonardi, F. Groppi, L. Gini, C. Mainardi, A. Ghioni, G. Ballarini, E. Menapace, K. Abbas, U. Holzwarth, M.F. Stroosnijder, J. Radioan. Nucl. Chem., 257 (2003) 229-241, Proceeding of 4th International Conference on Isotopes, Cape Town, South Africa - 2002.

2. E. Menapace, C. Birattari, M.L. Bonardi, F. Groppi, Rad. Phys. Chem., 71 (2004) 943-945.3. F. Groppi, M. Bonardi, C. Birattari, L. Gini, C. Mainardi, E. Menapace, K. Abbas, U. Holzwarth,

R.M.F. Stroosnijder, NIM-B, 213C (2004) 373-377.4. M.L. Bonardi, F. Groppi, H.S.C. Mainardi, V.M. Kokhanyuk, E.V. Lapshina, M.V. Mebel, B.L.

Zhuikov, J. Radioanal. Nucl. Chem., 264-1 (2005).5. E. Menapace, C. Birattari, M.L. Bonardi, F. Groppi, S. Morzenti, C. Zona, Proc. of Intern. Conf. on

Nuclear Data for Science and Technology., Santa Fe, USA (2004), American Institute of Physics, in press

6. F. Groppi, M.L. Bonardi, C. Birattari, E. Menapace, K. Abbas, U. Holzwarth, A. Alfarano, S. Morzenti, C. Zona, Z.B. Alfassi, Appl. Rad. Isot. (2005) in press.

7. A.Hermanne, F. Tarkanyi, S. Takàcs, Z. Szucs, Yu. N. Shubin, A. I. Dityuk, Appl. Rad. Isot. (2005) in press.

8. M. Herman, EMPIRE-II Statistical model code for nuclear reaction calculations (version 2.18), distributed by the IAEA Nuclear Data Section.

9. K. Abbas, A. Alfarano, Z. Alfassi, C. Apostolidis, C. Birattari, M. Bonardi, N. Gibson, F. Groppi, U. Holzwarth, E. Menapace, A. Morgenstern, S. Morzenti, H. Stamm, Development in alpha emitting radioisotope production at the Joint Research Centre (JRC) of the European Commission, Contr. Paper to the 17th Internat. Conf. on Cyclotrons and their Applications, Tokyo, Japan, October 2004.

REFERENCESREFERENCES


10. M. Bonardi, “The contribution to nuclear data for medical radioisotope production from the Milan Cyclotron Laboratory”, IAEA Consultants’s Meeting on “Nuclear Data Requirements for Medical Radioisotope Production”, Tokyo, Apr 1987 (Invited), INDC(NDS)-195/GZ, IAEA, Vienna, Austria, 1988, pp. 98-112.

11. D. Basile, C. Birattari, M. Bonardi, L. Goetz, E. Sabbioni, A. Salomone, Int. J. Appl. Rad. Isot., 32, 403-410 (1981).

12. E. Acerbi, C. Birattari, M. Bonardi, C. De Martinis, A. Salomone, Int. J. Appl. Rad. Isot., 32, 465-475 (1981).

13. M. Crippa, E. Gadioli, P. Vergani, G. Ciavola, C. Marchetta, M. Bonardi, Zeits. f. Phys. A, Hadrons and Nuclei, 350 (2), 121-129 (1994).

14. M. Bello, C. Bovati, A. Di Filippo, T.G. Stevens, S.H. Connell, J.P.F. Sellschop, S.J. Mills, F.M. Nortier, G.F. Steyn, C. Marchetta, C. Birattari, M. Bonardi, F. Groppi, Phys. Rev. C, 54 (6), 3051-3055 (1996).

15. M. Bonardi, C. Birattari, M. Gallorini, F. Groppi, D. Arginelli, L. Gini, J. Radioanal. Nucl. Chem., 236, 159-164 (1998).

16. F. Groppi, M. Bonardi, C. Birattari, M. Gallorini, L. Gini, J. Radioanal. Nucl. Chem., 249, 289-293 (2001).

17. C. Birattari, M. Bonardi, L. Gini, F. Groppi, E. Menapace, J. Nucl. Sci. Technol., Suppl. 2, 1302-1305 (2002).



18. F. Groppi, C. Birattari, M. Bonardi, H.S. Mainardi, E. Menapace, “A Method For Simultaneous Deuteron-Cyclotron Production Of NCA 64Cu And 66Ga, 67Ga For Application In PET Diagnostics And Metabolic Therapy Of Tumors”, Int. Conf. Isotopic Nucl. Anal. Techn. Health Environ., Vienna 10-13 June 2003, IAEA-CN- 103/108, CD-Rom10 pages.

19. E. Menapace, “Trends and progresses on nuclear data activities and international cooperation, according to the IAEA-International Nuclear Data Committee” (Invited), Int. Conf. Nucl. Data for Science and Technology Conference Proceeding, Gatlinburg, TN, 1994, pp. 18-24.

20. N. Shigeta, H. Matsuoka, A. Osa, M. Koizumi, M. Izumo, K. Kobayashi, K. Hashimoto, T. Sekine, R.M. Lambrecht, J. Radioanal. Nucl. Chem., 205, 85-92 (1996).

21. F.W. Pement, and R.L. Wolke, Nucl. Phys., 86, 429 (1966).22. S.J. Nassiff, and H. Munzel, Radiochim. Acta, 19(3), 97 (1973).23. T. Zhenlan, Z. Fuying, Q. Huiyuan, W. Gong Qing, Chin. J. Nucl. Phys. (in chinese), 3(3), 242,

(1981).24. E.L. Kelly, E. Segrè, Phys. Rev,. 75(7), 999-1005 (1949).25. W.J. Ramler, J. Winf, D.J. Henderson, J.R. Huizenga, Phys. Rev. 114(1), (1959) 154-162.26. R.M. Lambrecht, S. Mirzadeh, Int. J. Appl. Radiat. Isot. 36(6), 443-450 (1985).. 27. M. Frisoni, E. Menapace, A. Musumeci, E. Spezi, M. Vaccari, “Nuclear Data For Medical

Applications of Accelerators and Related Shielding Aspects”, Topical Meeting Nucl. Appl. Acc. Technol. Conf. Proceedings, Albuquerque, NM, USA, 1997, pp. 190-197.



THANK YOU THANK YOU FORFOR

YOUR KIND ATTENTIONYOUR KIND ATTENTION

5 th international conference on isotopes brussels, belgium, 25 – 29 april 2005

Documents

lasainfn laboratory

infnlasa laboratory

advanced physical technologies

isotopes brussels

recent activities

recent years activities

nuclear data

cyclotron laboratory