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
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
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.
Applied Nuclear Physics Group 4 32 P Production 31 P(n, ) 32 P cross section (JENDL)
Applied Nuclear Physics Group 5 32 P Decay 32 P decay scheme (MIRD)
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
Applied Nuclear Physics Group 7 32 P Decay β-spectrum : RADAR output (linear-scale fine energy bin) - the RAdiation Dose Assessment Resource
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
Applied Nuclear Physics Group 9 89 Sr Production 88 Sr(n, ) 89 Sr cross section (JENDL)
Applied Nuclear Physics Group Sr Decay 89 Sr decay scheme (MIRD)
Applied Nuclear Physics Group Sr Decay 89 Sr decay data (MIRD, RADLST)
Applied Nuclear Physics Group Sr Decay β-spectrum : RADAR output (linear-scale fine energy step)
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
Applied Nuclear Physics Group Te Production 130 Te(n, ) 131 Te cross section (JENDL)
Applied Nuclear Physics Group I Decay 131 I decay scheme (MIRD)
Applied Nuclear Physics Group I Decay 131 I decay data (MIRD, RADLST)
Applied Nuclear Physics Group 17
Applied Nuclear Physics Group I Decay β-spectrum : RADAR output (linear-scale fine energy step)
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
Applied Nuclear Physics Group Ho Production 165 Ho(n, ) 166 Ho cross section (JEF)
Applied Nuclear Physics Group Ho Decay 166 Ho decay scheme (MIRD)
Applied Nuclear Physics Group Ho Decay 166 Ho decay scheme (Isotope explorer)
Applied Nuclear Physics Group Ho Decay 166 Ho decay data (MIRD, RADLST)
Applied Nuclear Physics Group 24
Applied Nuclear Physics Group Ho Decay β-spectrum : RADAR output (linear-scale fine energy step)
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.
Applied Nuclear Physics Group Ir Production 191 Ir(n, ) 192 Ir cross section (ENDF, NGATLAS)
Applied Nuclear Physics Group Ir Decay 192 Ir decay scheme (MIRD)
Applied Nuclear Physics Group Ir Decay 192 Ir decay scheme (Isotope explorer)
Applied Nuclear Physics Group Ir Decay 192 Ir decay data (MIRD, RADLST)
Applied Nuclear Physics Group 31
Applied Nuclear Physics Group 32 β-spectrum : RADLST output (log–scale energy bin)
Applied Nuclear Physics Group 33 End.
Applied Nuclear Physics Group 34 추가 페이지 : 단면적 graph ( 전체 library 포함 )
Applied Nuclear Physics Group P Production 31 P(n, ) 32 P cross section
Applied Nuclear Physics Group Sr Production 88 Sr(n, ) 89 Sr cross section
Applied Nuclear Physics Group I Production 130 Te(n, ) 131 Te cross section
Applied Nuclear Physics Group Ho Production 165 Ho(n, ) 166 Ho cross section
Applied Nuclear Physics Group Ir Production 191 Ir(n, ) 192 Ir cross section