Assessment of Residual Radioisotopes Following F-18 Radionuclide - - PowerPoint PPT Presentation

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Assessment of Residual Radioisotopes Following F-18 Radionuclide - - PowerPoint PPT Presentation

Assessment of Residual Radioisotopes Following F-18 Radionuclide Production Imam Kambali Center for Radioisotope and Radiopharmaceutical Technology National Nuclear Energy Agency (BATAN) ICTP, Trieste, Italy Puspiptek Area, Serpong, South


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Center for Radioisotope and Radiopharmaceutical Technology National Nuclear Energy Agency (BATAN) Puspiptek Area, Serpong, South Tangerang, INDONESIA - 15314 Email: imamkey@batan.go.id

ICTP, Trieste, Italy Trieste, 2-13 October 2017

Assessment

  • f

Residual Radioisotopes Following F-18 Radionuclide Production

Imam Kambali

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  • 1. In

Introducti ction

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Fluorine-18 (F-18) is used in nuclear medicine for cancer diagnosis At Dharmais Cancer Hospital in Jakarta, F-18 is produced using an 11-MeV proton accelerating cyclotron F-18 production generates a vast number of secondary neutrons which are scattered off and/or transmitted into surrounding materials It could potentially generate residual radioisotopes in the cyclotron vicinity which eventually become major safety concerns over radiation exposure to the workers Radiation measurement and radioisotope identification are required

Proton beam H2

18O target

neutrons

18O(p,n)18F

Surrounding materials

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2.

  • 2. Exp

xperiment ments

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F-18 production was done using an 11-MeV cyclotron at Dharmais Cancer

Hospital in Jakarta, Indonesia Residual radionuclides in post-irradiated H2

18O were detected

Radiation in the cyclotron vicinity were detected, including the cyclotron’s shielding, cyclotron tank/chamber, cave wall as well as target system

Target system Inner surface of cyclotron shielding Outer surface of cyclotron shielding Outer surface of cyclotron chamber

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2.

  • 2. Exp

xperiment ments

06/03/2017 4 Eclipse 11 MeV Cyclotron Concrete wall Control room Cyclotron shielding UPS Power supply

11-MeV cyclotron cave in Dharmais Cancer Hospital, Jakarta

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2.

  • 2. Exp

xperiment ments

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Target system for F-18 production at Dharmais Cancer Hospital, Jakarta

Enriched water target

Proton beam

Havar window Silver body / tube Rear screws Collimator

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2.

  • 2. Exp

xperiment ments

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Radiation detection and measurement was performed using HPGe based gamma ray spectrometer and NaI based portable gamma ray spectrometer TALYS Evaluated Nuclear Data (TENDL 2015) were employed to study the origin of residual radioisotopes

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3.

  • 3. Results

ts and D Discuss cussion ion

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3.1 Gamma spectrum of residual radioisotopes detected in

Irradiated H2

18O

500 1000 1500 2000 100 200 300 400 500 600 700 800 energy (keV) intensity (counts) 1000 1500 2000 2500 3000 20 40 60

  • Sample was measured 2

days following F-18 production

  • Measurement was done

using HpGe based gamma spectroscopy system

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3.

  • 3. Results

ts and D Discuss cussion ion

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3.1 Residual Radioisotopes Detected in Irradiated H2

18O, 2

Days Following F-18 Production

Radio- nuclide T1/2 (days) Eγ (keV) Nuclear Reaction Source

57Co

271.8 122

60Ni(p,α)57Co; 58Ni(p,2p)57Co; 58Ni(n,2n)57Co

Havar

57Ni

1.496 511, 1378

58Ni(p,pn)57Ni; 58Ni(p,d)57Ni; 59Co(p,X)57Ni Havar 58Co

70.83 811

58Fe(p,n)58Co; 58Ni(n,p) 58Co; 59Co(n,2n) 58Co

Havar

54Mn

312.1 835

58Fe(n,p)54Mn; 55Mn(n,2n) 54Mn

Havar

56Co

77.24 847

56Fe(p,n)57Co; 56Fe(p,2n)57Co

Havar

55Co

0.730 931, 2557

58Ni(p,α)55Co

Havar

52Mn

5.591 936, 1434

52Cr(p,n)52Mn

Havar

48V

15.974 983, 1312

49Ti(p,2n)48V

Havar

110Ag

250 657, 885, 937

109Ag(n,γ)110Ag

Silver body

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3.

  • 3. Results

ts and D Discuss cussion ion

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3.1 Radiation Detected in the Outer Surface of the Cyclotron Chamber

0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 1.3 1.4 1.5 1000 2000 3000 4000 5000 6000 7000

intensity (count)

Energy (MeV) Mn-54 Annihilation peak (a) 5 10 15 20 25 30 100 200 300 400 500 600 700 800 900 Nuclear Cross-section (mbarn) Proton or Neutron Energy (MeV)

54Fe(n,p)54Mn 55Mn(n,2n)54Mn

(b)

54Cr(p,n)54Mn

(a) Gamma ray emissions detected in the outer surface of the cyclotron chamber (at 90o with respect to the incoming proton beam), and (b) TALYS-calculated nuclear cross-sections of 54Cr(p,n)54Mn,

54Fe(n,p)54Mn, and 55Mn(n,2n)54Mn reactions.

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3.

  • 3. Results

ts and D Discuss cussion ion

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3.2 Radiation Detected in the Inner Surface of the Shielding

(a) Gamma ray emissions detected in the inner surface of the Eclipse 11 cyclotron’s shielding (b) TALYS-calculated nuclear cross-sections of several trace elements present in the shielding and wall of the cyclotron cave in Dharmais Cancer Hospital, Jakarta

0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 1.3 1.4 1.5 2000 4000 6000 8000 10000 12000 14000 16000 intensity (count) Energy (MeV)

0.7 0.8 0.9 1 1.1 1.2 1.3 500 1000 1500 Mn-54 Zn-65

Zn-65 Mn-54 Annihilation peak

0.002 0.004 0.006 0.008 0.01 0.012 0.014 0.016 0.018 0.02 1 2 3 4 5 x 10

5

Cross-section (mbarn) Energy (MeV) 0.005 0.01 0.015 0.02 1000 2000 5 10 15 20 25 30 2000 4000 6000 8000 10000 Cross-section (mbarn) Energy (MeV) (2) (1) (1) (2) (5) (6) (7) (3) (4) (5) (6) 54Fe(n,p)54Mn (7) 55Mn(n,2n)54Mn (1) 151Eu(n,)152Eu (2) 133Cs(n,)134Cs (3) 45Sc(n,)46Sc (4) 59Co(n,)60Co (5) 64Zn(n,)65Zn

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3.

  • 3. Results

ts and D Discuss cussion ion

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3.2 Radiation Detected in the Outer Surface of the Shielding

(a) Gamma ray emissions detected in the outer surface

  • f the Eclipse 11 cyclotron’s shielding

(b) Angular distribution of the Eu-152 gamma ray intensities (c) TALYS-calculated nuclear cross-sections of several trace elements present in the shielding and wall of the cyclotron cave in Dharmais Cancer Hospital, Jakarta

0.002 0.004 0.006 0.008 0.01 0.012 0.014 0.016 0.018 0.02 1 2 3 4 5 x 10

5

Cross-section (mbarn) Energy (MeV) 0.005 0.01 0.015 0.02 1000 2000

(2) (1) (3) (4) (5)

(1) 151Eu(n,)152Eu (2) 133Cs(n,)134Cs (3) 45Sc(n,)46Sc (4) 59Co(n,)60Co (5) 64Zn(n,)65Zn

0.4 0.5 0.6 0.7 0.8 0.9 1 1.1 1.2 1.3 1.4 1.5 100 200 300 400 500 intensity (count)

Energy (MeV)

Annihilation peak Eu-152 (a)

  • 10

10 20 30 40 50 60 70 80 90 100 1 2 3 4 count rate (count/s) Angle (o) (b)

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3.

  • 3. Results

ts and D Discuss cussion ion

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3.3 Radiation Detected in the Target System 3.3.1 Havar window

(a) Gamma ray emissions detected in the Havar window, and (b) (b) TALYS-calculated nuclear cross-sections of possible proton-induced radionuclides

0.2 0.4 0.6 0.8 1 1.2 1.4 1 2 3 4 5x 10

4

intensity (count) Energy (MeV) Co-56 Annihilation peak Pb X-rays Co-56 (a)

2 4 6 8 10 12 14 16 18 20 200 400 600 800 1000

nuclear cross-section (mbarn)

proton ennergy (MeV) (b)

96Mo(p,n)96Tc 55Mn(p,n)55Fe

(7) (6) (5) (3) (2) (4) (1) (1) (2) (5) (4) (3) (6) (7)

59Co(p,n)59Ni 56Fe(p,n)56Co 52Cr(p,n)52Mn 184W(p,n)184Re 58Ni(p,n)58Cu

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3.

  • 3. Results

ts and D Discuss cussion ion

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3.3 Radiation Detected in the Target System 3.3.2 Collimator

Gamma ray emissions captured by the portable gamma ray spectrometry system from the collimator in the target system

0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.5 0.5 1 1.5 2 2.5 x 10

4

intensity (count) Energy (MeV) Co-56 Pb X-rays Annihilation peak Co-56

2 4 6 8 10 12 14 16 18 20 200 400 600 800 1000

nuclear cross-section (mbarn)

proton ennergy (MeV) (b)

96Mo(p,n)96Tc 55Mn(p,n)55Fe

(7) (6) (5) (3) (2) (4) (1) (1) (2) (5) (4) (3) (6) (7)

59Co(p,n)59Ni 56Fe(p,n)56Co 52Cr(p,n)52Mn 184W(p,n)184Re 58Ni(p,n)58Cu

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3.

  • 3. Results

ts and D Discuss cussion ion

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3.3 Radiation Detected in the Target System 3.3.3 Target Body

(a) Gamma ray emissions detected in the silver body, and (b) TALYS-calculated nuclear cross-sections

  • f

109Ag(n,γ)110mAg, 109Ag(p,n)109Cd

and

109Ag(p,2n)108Pd nuclear reactions

0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.55 0.5 1 1.5 2 x 10

5

intensity (count) Energy (MeV) 1.15 1.3 1.45 1 1.5 2 2.5 x 10

4

Ag-110m Ag-110m Pb X-ray Ag-110m (a) 0.2 0.4 0.6 0.8 1 x 10

  • 7

0.5 1 1.5 2 2.5 3 3.5 4 4.5 x 10

6

nuclear cross-section (mbarn) proton or neutron energy (MeV) 5 10 15 20 25 30 600 1200 1800 5 10 15 20 25 30 10 20 25 (b)

109Ag(p,2n)108Pd 109Ag(p,n)109Cd 109Ag(n,)110mAg

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3.

  • 3. Results

ts and D Discuss cussion ion

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3.3 Radiation Detected in the Target System 3.3.4 The Rear Screw

(a) Gamma ray emissions detected in the rear screw of the target system, and (b) TALYS-calculated nuclear cross-sections of 51Mn(n,γ)52Mn and 59Co(p,n)60Co

0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.55 500 1000 1500 2000 2500 3000 3500 intensity (count) Energy (MeV) 0.95 1.15 1.35 1.55 50 100 150 200 Annihilation peak Mn-54 Pb X-rays (a) Mn-52 Co-60 Co-60

1 2 3 4 x 10

  • 8

0.5 1 1.5 2 x 10

6

nuclear cross-section (mbarn) proton ennergy (MeV) 5 10 15 20 5 10

51Mn(n,)52Mn 59Co(n,)60Co

(b)

51Mn(n,)52Mn

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4.

  • 4. Co

Conclusion sion

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Proton and neutron induced by-products identified in the Dharmais Cancer Hospital, Jakarta

No Investigated Component/Point Observed Radionuclide Nuclear Reaction 1. Outer surface of the cyclotron chamber Mn-54

54Fe(n,p)54Mn

2. Inner and outer surface of the cyclotron shielding Zn-65 Mn-54 Eu-152

64Zn(n,γ)65Zn 54Fe(n,p)54Mn and/or 55Mn(n, 2n)54Mn 151Eu(n,γ)152Eu

3. Havar windows and collimator Co-56

56Fe(p,n)56Co

4. Silver body Ag-110m

109Ag(n,γ)110mAg

5. Rear screws Mn-52, Co-60, Mn-54

51Mn(n,γ)52Mn 59Co(n,γ)60Co 54Fe(n,p)54Mn and/or 55Mn(n, 2n)54Mn

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Thank nk Yo You Grazie Terima kasih