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Pr 139 Ce(p,2n) 140 GEANT4 TALYS اريخ دريافت ت70 / 70 / 9911 يخ پذيرش تار82 / 70 / 9911 PET PET PET Pr 139 Ce(p,2n) 140 TALYS GEANT4 Pr 139 Ce(p,2n) 140 TALYS GEANT4 SRIM GEANT4 SRIM GEANT4 MeV TALYS GEANT4 MeV Pr 139 Ce(p,2n) 140 MeV 1 - h 1 - MBqμA 140Ce(p,2n)139Pr TALYS GEANT4 SRIM GEANT4 TALYS Email: [email protected], [email protected] PET Positron Emission Tomography Downloaded from umj.umsu.ac.ir at 11:43 +0330 on Thursday October 7th 2021 [ DOI: 10.29252/umj.31.9.680 ]

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Page 1: CALCULATION OF CROSS SECTION AND PRODUCTION YIELD OF

Pr139Ce(p,2n)140

GEANT4 TALYS

82/70/9911تاريخ پذيرش 70/70/9911تاريخ دريافت

PET

PET

PETPr139Ce(p,2n)140

TALYSGEANT4

Pr139Ce(p,2n)140 TALYSGEANT4

SRIMGEANT4

SRIMGEANT4

MeV

TALYSGEANT4 MeV

Pr139Ce(p,2n)140

MeV 1-h1-MBqµA

140Ce(p,2n)139Pr

TALYSGEANT4SRIM

GEANT4 TALYS

Email: [email protected], [email protected]

PET

Positron Emission Tomography

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N.I.H

St.Louis

PET

HSA

PET

National Institutes of Health

Human Serum Albumin

Spherical Optical Model Potential

Back-Shifted Fermi Gas Model

Pr139Pr142g

Pr139

Pr139Ce(p,2n)140

MeV

Furukawa

Zeisler

MeV

Pr 139Ce(p,2n)140

TALYS GEANT4

TALYS

OMPs

BSFGMCGCM

GSM

.

SRIM

Composite Gilbert-Cameron Model

Generalized Superfluid Model

Stopping and Range of Ions in Matter

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Page 3: CALCULATION OF CROSS SECTION AND PRODUCTION YIELD OF

TALYS1.95TALYS

TALYS

He 3keV

MeV

TALYS

TALYS

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(1 )( ) ( ) ( )U r V r iW r

V(r)W(r)

V(r)

W(r)

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Level Density Model

Constant Temperature Model

J

MeVxE

( ) ( , , )tot

x x

J

E E J

)2(

BSFGM

CTMCGCM

GSM

BSFGM

1 5

4 4

exp 21( )

122

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F x

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)3(

aU

ExU

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CGCM:

0 )1( ) exptot x

CGC x

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1( )

2

Stot

GS x

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)6(

SD σ

a

1 e( ) 1

U

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Page 5: CALCULATION OF CROSS SECTION AND PRODUCTION YIELD OF

SRIMGEANT4

140Ce(p,2n)139Pr

TALYS

GEANT4MeV

BSFGMOMPs

CGCMGSMTALYS

MeVMeV

MeV

MeV

TALYSPr139Ce(p,2n)140

140Ce(p,2n)139PrGEANT4

TALYS

Zeisler

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Page 6: CALCULATION OF CROSS SECTION AND PRODUCTION YIELD OF

MeV

GEANT4

TALYS

140Ce(p,2n)139Pr

GEANT4

GEANT4

140Ce(p,2n)139Pr

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TALYSGEANT4

Zeisler

MeV

MBqµA-1h-1

TALYSGEANT4140Ce(p,2n)139Pr

MeV

TALYSGEANT4

MBqµA-1h-1

MeV

Geant4

MeV

MeV

GEANT4TALYS

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Page 8: CALCULATION OF CROSS SECTION AND PRODUCTION YIELD OF

140Ce(p,2n)139PrTALYS

GEANT4SRIM

MeV

TALYSGEANT4

Zeisler

TALYSGEANT4

MeV

140Ce(p,2n)139Pr

TALYSGEANT4

MBqμA-1A-1

MBqμA-1A-1

TALYS

GEANT4

TALYSGEANT4

GEANT4

TALYSGEANT4 SRIM

References:

1. Smith B. Nuclear Pharmacy.1th ed. London:

Pharmaceutical Press; 2010.

2. Fricker SP. The therapeutic application of lanthanides.

Chem. Soc. Rev 2006; 6: 524-33.

3. Zeisler SK, Becker DW. A new method for PET

imaging of tumours: human serum albumin labeled with the

long-lived 140Nd/139Pr in vivo radionuclide generator. Clin

Positron Imaging 1999; 2: 324.

4. Kaczmarek MT, Zabiszak M, Nowak M, Jastrzab R.

Lanthanides: Schiff base complex, applications in cancer

diagnosis, therapy and antibacterial activity. Coord Chem Rev

2018; 370: 42-54.

5. Teo RD, Termini J, Gray HB. Lanthanides:

Applications in cancer diagnosis and therapy. J Med Chem

2016; 59: 6012-24.

6. Steyn GF, Vermeulen C, Noritier FM, Szelecsenyi F,

Kovacs Z. Production of no-carrier-added 139Pr via precursor

decay in the proton bombardment of natPr. Nucl Instrum

Methods Phys Res B 2006; 252: 149-59.

7. Furukawa M. Excitation functions for proton-induced

reactions of 140Ce and 142Ce up to Ep=15 MeV. Nucl Phys A

1967; 67: 253-60.

8. Zeisler K, Becker DW. A pellet method for the

measurement of excitation functions: Cross-section for

140Ce(p,2n)139Pr and 140Ce(p,3n)138mPr, Nucl Instrum Methods

Phys Res B 2000; 160: 216-20.

9. Ziegler JF. SRIM & TRIM [Internet]. [cited 2020 Dec

22]. Available from: http://www.srim.org/

10. Ziegler J, Andersen H. Helium stopping powers and

ranges in All element. NewYork: Pergamon; 1977.

11. Rostampour M, Aboudzadeh MR, Sadeghi M, Hamidi

S. Theoretical assessment of production routes for 63Zn by

cyclotron. J Radioanal Nucl Chem 2016;309:677-84.

12. Koning A, Hilaire S, Goriely S. TALYS1.95 A

nuclear reaction program User manual. 1th ed. Netherlands:

NRG; 2019.

13. Kakavand T, Mirzaii M, Eslami M, Karimi A. Nuclear

model calculation and targetry recipe for production of 110mIn.

Appl Radiat Isot 2015; 104: 60-6.

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14. Eslami M, Kakavand T. Simulation of the direct

production of 99mTc at a small cyclotron. Nucl Instrum

Methods Phys Res B 2014; 329: 18-21

15. Sharifian M, Sadeghi M, Alimohamadi M.

Calculation of 89Y(p,x)86,88,89gZr,86g,87g,88gY,85gSr,and 84Rb

reaction cross sections based on level density. Appl Radiat

Isot 2019; 151: 25-9.

16. Rostampour M, Sadeghi M, Aboudzadeh MR, Hamidi

S, Hosseini SF. Validation of GEANT4 simulations for 62,63Zn

yield estimation in proton induced reactions of natural copper.

Nucl Instrum Methods Phys Res B 2017; 394: 141-4.

17. Poignant F, Penfold S, Asp J, Takhar P, Jackson P.

GEANT4 simulation of cyclotron radioisotope production in

a solid target, Med Phys 2016; 32: 728-34.

18. Cirrone GAP, Cuttone G, Dirose F, Pandola L,

Romano F, Zhang Q. Validation of the Geant4

electromagnetic photon cross-section for elements and

compounds. Nucl Instrum Methods Phys Res A 2010; 618:

315-22.

19. User Documentation | geant4.web.cern.ch [Internet].

[cited 2020 Dec 22]. Available from:

https://geant4.web.cern.ch/support/user_documentation

.

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Page 10: CALCULATION OF CROSS SECTION AND PRODUCTION YIELD OF

Studies in Medical Sciences, Vol. 31(9), December 2020

Original Article

CALCULATION OF CROSS SECTION AND PRODUCTION YIELD OF

RADIOPHARMACEUTICAL PRASEODYMIUM-139 THROUGH 140CE(P, 2N)139PR REACTION USING GEANT4 AND TALYS NUCLEAR

CODES

Farzad Isazadeh1, Akbar Abdi saray2*

Received: 26 June, 2020; Accepted: 18 October, 2020

Abstract

Background & Aim: PET is a very useful and suitable imaging method in nuclear medicine. This

method uses positrons with a special energy for imaging. The elements of the lanthanide are suitable for

the decay of positrons with a specific energy for use in PET. Praseodymium-139 with a half-life of 4.5

hours is one of the useful elements in the group of lanthanides that can be used in PET. In this study,

the 140Ce (p,2n)139Pr reaction to produce the useful radiopharmaceutical Praseodymium-139 was

simulated by the TALYS code with four different models and also by the GEANT4 Monte Carlo code.

The purpose of this simulation is to calculate the cross-sectional area of the reaction and the production

efficiency of praseodymium-139 in the proton irradiated cerium-140 target.

Materials & Methods: The values of cross-section and production yield of Praseodymium-139 have

been obtained through 140Ce(p,2n)139Pr reaction using TALYS and GEANT4 codes and the proton

projectile range changes in the cerium-140 target were simulated using SRIM and GEANT4 codes.

Results: Proton range changes are shown using the SRIM and GEANT4 codes in the Cerium-140 target

for different energies of the entrance protons. The range of protons in cerium-140 at 22 MeV energy

was calculated to be 1610 and 1637.5 micrometers, respectively. Then the cross-sectional values

simulated using TALYS and GEANT4 codes for different energies of the entrance protons were

compared with the experimental data. At the energy of 5.22 MeV, the cross section of Praseodymium-

139 has the maximum amount in the reaction 140Ce(p,2n)139Pr. The thickness of the production thickness

was calculated from the target of cerium-140 for different proton energies. The cross-sectional values

obtained in this energy using these two codes are 1150.7 and 1350.4 bar, respectively. Also, the amount

of product yield in the energy of 22 MeV was calculated using these codes, 1832.1 and 1782.83 MBqµA-

1h-1, respectively.

Discussion and conclusion: Comparison of the simulation results for the product of praseodymium-139

radiopharmaceuticals through the 140Ce(p,2n)139Pr reaction using the TALYS code and the GEANT4

and SRIM Monte Carlo methods show that they are in good agreement with the experimental data. It is

also possible to simulate the desired reaction using these codes without spending a lot of time and money

and laboratory materials and before the production of radiopharmaceuticals, and to predict the values of

production efficiency and the appropriate range of energy for the production of radiopharmaceuticals.

Keywords: Praseodymium-139, GEANT4 code, TALYS code, cross section, production efficiency,

accelerator.

Address: Department of Physics, Faculty of Science, Urmia University, Urmia, Iran.

Tel: +984431942042

Email: [email protected], [email protected]

SOURCE: STUD MED SCI 2020: 31(9): 689 ISSN: 2717-008X

1 MSc Student, Department of physics, Faculty of Science, Urmia University, Urmia, Iran 2 Assistant Professor, Department of physics, Faculty of Science, Urmia University, Urmia, Iran (Corresponding

Author)

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