Neutron (n, ) Cross Section and Decay Data for 32 P, 89 Sr, 131 I, 166 Ho, 192 Ir

39
Applied Nuclear Physic The 2 nd meeting of IAEA CRP 2004. 11. 15-19 Neutron (n, ) Cross Section and Decay Data for 32 P, 89 Sr, 131 I, 166 Ho, 192 Ir H.D. Choi, S.K. Kim, C.S. Park Department of Nuclear Engineering, Seoul National University, Korea Nuclear Data for Production of Therapeutic Radionuclides

description

The 2 nd meeting of IAEA CRP 2004. 11. 15-19. Neutron (n,  ) Cross Section and Decay Data for 32 P, 89 Sr, 131 I, 166 Ho, 192 Ir. Nuclear Data for Production of Therapeutic Radionuclides. H.D. Choi, S.K. Kim, C.S. Park - PowerPoint PPT Presentation

Transcript of Neutron (n, ) Cross Section and Decay Data for 32 P, 89 Sr, 131 I, 166 Ho, 192 Ir

Page 1: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

Applied Nuclear Physics Group

The 2nd meeting of IAEA CRP 2004. 11. 15-19

Neutron (n, ) Cross Section and Decay Data for 32P, 89Sr, 131I, 166Ho, 192Ir

H.D. Choi, S.K. Kim, C.S. Park

Department of Nuclear Engineering, Seoul National University, Korea

Nuclear Data for Production of Therapeutic Radionuclides

Page 2: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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CRP Workscope

Radioisotopes : 32P, 89Sr, 131I, 166Ho, 192Ir

- HANARO research reactor in KAERI, KOREA

- Medical application in Korea

- Neutron cross sections

: ENDF, JENDL, JEF library

- Decay data

: MIRD, RADLST, RADAR database

Page 3: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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32P Production

31P(n, )32P cross section

Library

(2200 m/s)

[b]

Resonance integral

[b]

Resonance region b

Fast cross section a [b]

14 MeV Fission

spectrum c

BNL-325 0.172(6) 0.085(10) Exp.

(Parameter)- -

ENDF/B-VI 0.1991 0.1452 a - 3.00010-4 1.47310-3

JEF-2 0.1664 a 0.07569 a Eval. 9.89510-6 1.01210-3

JENDL-3 0.166 0.081 Eval. 9.89510-6 1.01210-3

BROND-2 0.181 0.087 Eval. 3.00010-4 1.20510-3

CENDL-2 0.1741 0.06071 a Eval. 1.84910-4 1.42310-3

a JEF Report 14 (1994). b Exp. : experimental data parameterized, Eval. : evaluated data in resonance region. c Maxwellian spectrum with T=1.35 MeV and integration limits 1 keV – 20 MeV.

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32P Production

31P(n, )32P cross section (JENDL)

Page 5: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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32P Decay

32P decay scheme (MIRD)

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32P Decay

32P decay data (MIRD, RADLST)

note) y : yield [#/Bq·s] (numbers of -transition per decay)

E : average energy for , radiation energy for others [MeV]

Emax : -maximum energy [MeV]

DCF : Dose Conversion Factor [g·rad/μCi·h]

DCF is given 0(zero) for values less than 10-4.

Half-life

Radiation No. y [(Bq·s) 1

] E [MeV] y*E Emax [MeV] DCF

β

1 1.00( ) 0.6949(3) 0.6949 1.71066(21) 1.48

0.6949 1.48

0.6949 1.48

14.262(14) d

Listed , ce and Auger Radiations

Listed Radiations

Page 7: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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32P Decay

β-spectrum : RADAR output (linear-scale fine energy bin)

- the RAdiation Dose Assessment Resource

Page 8: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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89Sr Production

88Sr(n, )89Sr cross section

Library

(2200 m/s)

[b]

Resonance integral

[b]

Resonance region b

Fast cross section a [b]

14 MeV Fission

spectrum

BNL-325 0.0058(4) 0.05(2) Parameter - -

ENDF/B-VI 0.006 0.012 a Eval. 1.59510-3 1.27510-2

JEF-2 0.005807 a 0.005764 a - 1.59510-3 1.27510-2

JENDL-3 0.0058 0.0633 Eval. 1.00410-3 2.34510-2

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89Sr Production

88Sr(n, )89Sr cross section (JENDL)

Page 10: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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89Sr Decay

89Sr decay scheme (MIRD)

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89Sr Decay

89Sr decay data (MIRD, RADLST)Half-life

Radiation No. y [(Bq·s) 1

] E [MeV] y*E Emax [MeV] DCF

β

1 0.0000964(5) 0.1890(10) 0.0000182 0.5861(22) 0

β

2 0.9999038(5) 0.5846(10) 0.585 1.4951(22) 1.25 1 0.0000956(5) 0.90896(3) 0.0000869 0.0002

CE-K 1 6.93E-07(2) 0.8919(3) 6.18E-07 0

CE-L 1 8.41E-08(3) 0.9066(3) 7.63E-08 0

Kα1 X-ray 2.75E-07(9) 0.01496(20) 4.11E-09 0

Kα2 X-ray 1.43E-07(5) 0.01488(20) 2.13E-09 0

Kβ X-ray 7.85E-08(3) 0.0167 1.31E-09 0

L X-ray 2.41E-08(6) 0.00192 4.63E-11 0

Auger-K 1.97E-07(5) 0.0127 2.50E-09 0

Auger-L 8.10E-07(6) 0.00191 1.55E-09 0

8.69E-05 0.0002

0.585 1.25

0.585 1.25

50.53(7) d

Listed X, Radiations

Listed β, ce and Auger Radiations

Listed Radiations

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89Sr Decay

β-spectrum : RADAR output (linear-scale fine energy step)

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131Te - 131I Production

130Te(n, )131Te cross section

Library

(2200 m/s)

[b]

Resonance integral

[b]

Resonance region b

Fast cross section a [b]

14 MeV Fission

spectrum c

BNL-325 0.290(60) 0.61(20) Parameter - -

ENDF/B-VI 0.290 0.354 Eval. 1.94710-3 4.48110-3

JEF-2 0.2903 a 0.363 a Eval. 1.94710-3 4.47610-3

JENDL-3 0.2700 0.285 Eval. 1.00010-3 5.56010-3

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131Te Production

130Te(n, )131Te cross section (JENDL)

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131I Decay

131I decay scheme (MIRD)

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131I Decay

131I decay data (MIRD, RADLST)Half-life

Radiation No. y [(Bq·s) 1

] E [MeV] y*E Emax [MeV] DCF

β

1 0.0210(3) 0.06936(19) 0.00146 0.2479(6) 0.0031

β

2 0.00651(23) 0.08694(20) 0.000566 0.3039(6) 0.0012

β

3 0.0727(10) 0.09662(20) 0.00702 0.3338(6) 0.015

β

4 0.899(8) 0.19158(23) 0.172 0.6063(6) 0.367

β

5 0.00050(23) 0.20022(23) 0.0001 0.6297(6) 0

β

6 0.00480(10) 0.28324(23) 0.00136 0.8069(6) 0.0029

ce-K 1 0.0354(20) 0.04562(16) 0.00162 0.0034

ce-L 1 0.00464(21) 0.07473(21) 0.000347 0.0007

ce-K 6 0.00252(17) 0.2497() 0.000628 0

ce-K 13 0.0155(20) 0.3299() 0.00512 0

ce-L 13 0.00246(22) 0.3590() 0.000883 0 1 0.0262(4) 0.080185(2) 0.0021 0.0045 3 0.00270(4) 0.177214(2) 0.000478 0 6 0.0614(7) 0.284305(5) 0.0174 0.0003

8.02070(11) d

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11 0.00274(22) 0.325789(4) 0.000892 0.0001 13 0.817(8) 0.364489(5) 0.298 0.0001 15 0.00360(4) 0.503004(4) 0.00181 0.0005 16 0.0717(10) 0.636989(4) 0.0457 0 17 0.00217(5) 0.642719(5) 0.0014 0.0039 18 0.0177(3) 0.722911(5) 0.0128 0.0973

Kα1 X-ray 0.0255(11) 0.029779(1) 0.00076 0.0016

Kα2 X-ray 0.0138(6) 0.029458(1) 0.000406 0.0009

0.382 0.1092

1.11E-03

0.191 0.3933

1.32E-03

0.573 0.5025

Omitted β, ce and Auger Radiations

Listed Radiations

Each omitted transition contributes <0.1 % to Σ(y*E) in its category

Listed X, Radiations

Omitted X, Radiations

Listed β, ce and Auger Radiations

Page 18: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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131I Decay

β-spectrum : RADAR output (linear-scale fine energy step)

Page 19: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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166Ho Production

165Ho(n, )166Ho cross section

Library

(2200 m/s)

[b]

Resonance integral

[b]

Resonance region b

Fast cross section a [b]

14 MeV Fission

spectrum c

BNL-325 66.5(33) 700(20) Parameter - -

ENDF/B-VI 64.700 720.2 Eval. 1.27610-3 0.1220

JEF-2 66.59 a 761.4 a Eval. 2.61910-3 0.1460

Page 20: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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166Ho Production

165Ho(n, )166Ho cross section (JEF)

Page 21: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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166Ho Decay

166Ho decay scheme (MIRD)

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166Ho Decay

166Ho decay scheme (Isotope explorer)

Page 23: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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166Ho Decay

166Ho decay data (MIRD, RADLST)Half-life

Radiation No. y [(Bq·s) 1

] E [MeV] y*E Emax [MeV] DCF

β

1 0.000362(11) 0.0059(3) 2.14E-06 0.0234(11) 0

β

2 0.00307(8) 0.0519(4) 1.59E-04 0.1914(11) 0.0003

β

3 0.0000242 0.1051(4) 2.54E-06 0.3257(12) 0

β

4 0.0095 0.1149 0.00109 0.3940(11) 0.0023

β

5 0.000061(12) 0.3690(5) 2.25E-05 1.0680(11) 0

β

6 0.487(21) 0.6509(5) 0.317 1.7733(11) 0.675

β

7 0.500(21) 0.6936(5) 0.347 1.8539(11) 0.739

ce-K 1 0.115(5) 0.023088(8) 0.00265 0.0056

ce-L 1 0.265(10) 0.070823(8) 0.0188 0.04

ce-M 1 0.064(4) 0.078368(8) 0.00505 0.0108

ce-N 1 0.0176(7) 0.080125(8) 0.00141 0.003 1 0.0671(8) 0.080574(8) 0.00541 0.0115 2 0.000020(2) 0.18440(10) 3.69E-06 0 4 0.000194(22) 0.67400(4) 0.000131 0.0003

26.8(2) h

Page 24: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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5 0.000131(5) 0.70530(4) 0.0000924 0.0002 6 0.000119(5) 0.78589(3) 0.0000935 0.0002 7 0.000014(2) 1.26308(20) 1.77E-05 0 8 0.0093(3) 1.37940(6) 0.0128 0.0273 12 0.00187(4) 1.58189(8) 0.00296 0.0063 13 0.001200(20) 1.66248(8) 0.00199 0.0042 14 0.000277(5) 1.74991(6) 0.000485 0.001 15 0.000085(3) 1.83049(7) 0.000156 0.0003

Kα1 X-ray 0.0548(24) 0.0491277(4) 0.00269 0.0057

Kα2 X-ray 0.0309(14) 0.0482211(4) 0.00149 0.0032

Kβ X-ray 0.0224(10) 0.0557 0.00125 0.0027

L X-ray 0.0784(22) 0.00695 0.000545 0.0012

Auger-K 0.0066(3) 0.0387 2.55E-04 0.0006

Auger-L 0.283(8) 0.0055 0.00156 0.0033

0.0301 0.064

4.03E-05

0.694 1.48

4.69E-04

0.724 1.544

Omitted β, ce and Auger Radiations

Listed Radiations

Each omitted transition contributes <0.1 % to Σ(y*E) in its category

Listed X, RadiationsOmitted X, Radiations

Listed β, ce and Auger Radiations

Page 25: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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166Ho Decay

β-spectrum : RADAR output (linear-scale fine energy step)

Page 26: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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192Ir Production

191Ir(n, )192Ir cross section

Library

(2200 m/s)

[b]

Resonance integral

[b]

Resonance region b

Fast cross section a [b]

14 MeV Fission

spectrum c

BNL-325 924(53) 3750(200) Parameter - -

ENDF/B-VI 954.34 3551.5 Eval. 6.08010-3 *) 0.1830 *)

*) Calculated by using INTER code.

Page 27: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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192Ir Production

191Ir(n, )192Ir cross section (ENDF, NGATLAS)

Page 28: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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192Ir Decay

192Ir decay scheme (MIRD)

Page 29: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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192Ir Decay

192Ir decay scheme (Isotope explorer)

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192Ir Decay

192Ir decay data (MIRD, RADLST)Half-life

Radiation No. y [(Bq·s) 1

] E [MeV] y*E Emax [MeV] DCF

β

1 0.000035(5) 0.0136(5) 4.76E-07 0.0535(19) 0

β

2 0.000039(17) 0.0195(5) 7.60E-07 0.0757(19) 0

β

3 0.00103(3) 0.0211(5) 2.17E-05 0.0817(19) 0

β

4 0.0560(3) 0.0716(6) 0.00401 0.2587(19) 0.0085

β

5 0.4143(20) 0.1621(7) 0.0672 0.5388(19) 0.143

β

6 0.480(3) 0.2099(7) 0.101 0.6751(19) 0.215

ce-K, 4 0.0188(7) 0.2175617(8) 0.00409 0.0087

ce-L, 4 0.0088(4) 0.2820766(5) 0.00247 0.0053

ce-M, 4 0.00220(7) 0.2926606(10) 0.000645 0.0014

ce-K, 5 0.0180(7) 0.2300603(8) 0.00415 0.0088

ce-L, 5 0.0078(5) 0.2945752(5) 0.00229 0.0049

ce-M, 5 0.00195(9) 0.3051591(10) 0.000595 0.0013

ce-K, 6 0.0444(15) 0.2381114(8) 0.0106 0.0225

ce-L, 6 0.0195(9) 0.3026263(5) 0.00591 0.0126

73.827(11) d

Page 31: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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ce-M, 6 0.00489(17) 0.3132102(10) 0.00153 0.0033

ce-N+, 6 0.00145(8) 0.3157842(7) 0.000457 0.001

ce-K, 8 0.0102(5) 0.3896740(8) 0.00397 0.0085

ce-L, 8 0.00295(10) 0.4541889(5) 0.00134 0.0029

ce-M, 8 0.00072(4) 0.4647729(10) 0.000336 0.0007

ce-K, 10 0.000583(23) 0.5101862(10) 0.000297 0.0006

ce-K, 13 0.00175(13) 0.5260164(8) 0.000919 0.002

ce-K, 14 0.00064(5) 0.5340674(8) 0.000339 0.0007 4 0.2872(14) 0.29595654(15) 0.085 0.181 5 0.2968(15) 0.30845514(17) 0.0916 0.195 6 0.8271(21) 0.31650623(17) 0.262 0.558 7 0.00669(21) 0.4164688(7) 0.00279 0.0059 8 0.4781(24) 0.4680688(3) 0.224 0.477 10 0.04517(22) 0.5885811(7) 0.0266 0.0566 13 0.0820(4) 0.6044111(3) 0.0496 0.106 14 0.0534(8) 0.6124622(3) 0.0327 0.0697 16 0.00291(7) 0.8845366(7) 0.00257 0.0055

Kα1 X-ray 0.0455(9) 0.0668320(20) 0.00304 0.0065

Kα2 X-ray 0.0266(5) 0.0651220(20) 0.00173 0.0037

Kβ X-ray 0.0197(4) 0.07570() 0.00149 0.0032

Auger-L 0.0800(13) 0.00724() 0.000579 0.0012

Page 32: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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0.812 1.6681

4.24E-03

0.0424 0.4529

2.60E-03

0.854 2.121Listed Radiations

Each omitted transition contributes <0.1 % to Σ(y*E) in its category

Listed X, Radiations

Omitted X, Radiations

Listed β, ce and Auger Radiations

Omitted β, ce and Auger Radiations

β-spectrum : RADLST output

(log–scale energy bin)

Page 33: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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End.

Page 34: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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추가 페이지 : 단면적 graph ( 전체 library 포함 )

Page 35: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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32P Production

31P(n, )32P cross section

Page 36: Neutron (n,    ) Cross Section and Decay Data for     32 P,  89 Sr,  131 I,  166 Ho,  192 Ir

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89Sr Production

88Sr(n, )89Sr cross section

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131I Production

130Te(n, )131Te cross section

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166Ho Production

165Ho(n, )166Ho cross section

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192Ir Production

191Ir(n, )192Ir cross section