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Applied Nuclear Physics Group 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,

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Presentation on theme: "Applied Nuclear Physics Group 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,"— Presentation transcript:

1 Applied Nuclear Physics Group The 2 nd meeting of IAEA CRP 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

2 Applied Nuclear Physics Group 2 CRP Workscope  Radioisotopes : 32 P, 89 Sr, 131 I, 166 Ho, 192 Ir - HANARO research reactor in KAERI, KOREA - Medical application in Korea - Neutron cross sections : ENDF, JENDL, JEF library - Decay data : MIRD, RADLST, RADAR database

3 Applied Nuclear Physics Group 3 32 P Production  31 P(n,  ) 32 P cross section Library   (2200 m/s) [b] Resonance integral [b] Resonance region b Fast cross section a [b] 14 MeV Fission spectrum c BNL (6)0.085(10) Exp. (Parameter) -- ENDF/B-VI a   JEF a a Eval   JENDL Eval   BROND Eval   CENDL a Eval   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.

4 Applied Nuclear Physics Group 4 32 P Production  31 P(n,  ) 32 P cross section (JENDL)

5 Applied Nuclear Physics Group 5 32 P Decay  32 P decay scheme (MIRD)

6 Applied Nuclear Physics Group 6 32 P Decay  32 P decay data (MIRD, RADLST) note) y : yield [#/Bq·s] (numbers of  -transition per decay) E : average energy for , radiation energy for others [MeV] E max :  -maximum energy [MeV] DCF : Dose Conversion Factor [g·rad/μCi·h] DCF is given 0(zero) for values less than

7 Applied Nuclear Physics Group 7 32 P Decay  β-spectrum : RADAR output (linear-scale fine energy bin) - the RAdiation Dose Assessment Resource

8 Applied Nuclear Physics Group 8 89 Sr Production  88 Sr(n,  ) 89 Sr cross section Library   (2200 m/s) [b] Resonance integral [b] Resonance region b Fast cross section a [b] 14 MeV Fission spectrum BNL (4)0.05(2)Parameter-- ENDF/B-VI a Eval   JEF a a   JENDL Eval   10 -2

9 Applied Nuclear Physics Group 9 89 Sr Production  88 Sr(n,  ) 89 Sr cross section (JENDL)

10 Applied Nuclear Physics Group Sr Decay  89 Sr decay scheme (MIRD)

11 Applied Nuclear Physics Group Sr Decay  89 Sr decay data (MIRD, RADLST)

12 Applied Nuclear Physics Group Sr Decay  β-spectrum : RADAR output (linear-scale fine energy step)

13 Applied Nuclear Physics Group Te I Production  130 Te(n,  ) 131 Te cross section Library   (2200 m/s) [b] Resonance integral [b] Resonance region b Fast cross section a [b] 14 MeV Fission spectrum c BNL (60)0.61(20)Parameter-- ENDF/B-VI Eval   JEF a a Eval   JENDL Eval   10 -3

14 Applied Nuclear Physics Group Te Production  130 Te(n,  ) 131 Te cross section (JENDL)

15 Applied Nuclear Physics Group I Decay  131 I decay scheme (MIRD)

16 Applied Nuclear Physics Group I Decay  131 I decay data (MIRD, RADLST)

17 Applied Nuclear Physics Group 17

18 Applied Nuclear Physics Group I Decay  β-spectrum : RADAR output (linear-scale fine energy step)

19 Applied Nuclear Physics Group Ho Production  165 Ho(n,  ) 166 Ho cross section Library   (2200 m/s) [b] Resonance integral [b] Resonance region b Fast cross section a [b] 14 MeV Fission spectrum c BNL (33)700(20)Parameter-- ENDF/B-VI Eval  JEF a a Eval 

20 Applied Nuclear Physics Group Ho Production  165 Ho(n,  ) 166 Ho cross section (JEF)

21 Applied Nuclear Physics Group Ho Decay  166 Ho decay scheme (MIRD)

22 Applied Nuclear Physics Group Ho Decay  166 Ho decay scheme (Isotope explorer)

23 Applied Nuclear Physics Group Ho Decay  166 Ho decay data (MIRD, RADLST)

24 Applied Nuclear Physics Group 24

25 Applied Nuclear Physics Group Ho Decay  β-spectrum : RADAR output (linear-scale fine energy step)

26 Applied Nuclear Physics Group Ir Production  191 Ir(n,  ) 192 Ir cross section Library   (2200 m/s) [b] Resonance integral [b] Resonance region b Fast cross section a [b] 14 MeV Fission spectrum c BNL (53)3750(200)Parameter-- ENDF/B-VI Eval  *) *) *) Calculated by using INTER code.

27 Applied Nuclear Physics Group Ir Production  191 Ir(n,  ) 192 Ir cross section (ENDF, NGATLAS)

28 Applied Nuclear Physics Group Ir Decay  192 Ir decay scheme (MIRD)

29 Applied Nuclear Physics Group Ir Decay  192 Ir decay scheme (Isotope explorer)

30 Applied Nuclear Physics Group Ir Decay  192 Ir decay data (MIRD, RADLST)

31 Applied Nuclear Physics Group 31

32 Applied Nuclear Physics Group 32  β-spectrum : RADLST output (log–scale energy bin)

33 Applied Nuclear Physics Group 33 End.

34 Applied Nuclear Physics Group 34 추가 페이지 : 단면적 graph ( 전체 library 포함 )

35 Applied Nuclear Physics Group P Production  31 P(n,  ) 32 P cross section

36 Applied Nuclear Physics Group Sr Production  88 Sr(n,  ) 89 Sr cross section

37 Applied Nuclear Physics Group I Production  130 Te(n,  ) 131 Te cross section

38 Applied Nuclear Physics Group Ho Production  165 Ho(n,  ) 166 Ho cross section

39 Applied Nuclear Physics Group Ir Production  191 Ir(n,  ) 192 Ir cross section


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