Applied Nuclear Physics Group The final meeting of IAEA CRP 2006. 5. 29 – 6. 2 Calculation and Evaluation of (n,  ) Cross Sections for Producing 32 P,

Slides:



Advertisements
Similar presentations
Combined evaluation of PFNS for 235 U(n th,f), 239 Pu(n th,f), 233 U(n th,f) and 252 Cf(sf) (in progress) V.G. Pronyaev Institute of Physics.
Advertisements

 -Ray Emission Probabilities Edgardo Browne Decay Data Evaluation Project Workshop May 12 – 14, 2008 Bucharest, Romania.
Neutron Activation Decay Data Richard B. Firestone Isotopes Project, Lawrence Berkeley National Laboratory, Berkeley, CA DDEP Workshop 8-10 October.
EMERALD1: A Systematic Study of Cross Section Library Based Discrepancies in LWR Criticality Calculations Jaakko Leppänen Technical Research Centre of.
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,
Total Monte Carlo and related applications of the TALYS code system Arjan Koning NRG Petten, the Netherlands Technical Meeting on Neutron Cross- Section.
ACADs (08-006) Covered Keywords Radioactivity, radioactive decay, half-life, nuclide, alpha, beta, positron. Description Supporting Material
Experimental Determination of Neutron Cross Sections of Yttrium by Activation Method by Barbara Geier Supervisors: Assoc. Prof Dr. Wolfgang Sprengel RNDr.
I. Dillmann Institut für Kernphysik, Forschungszentrum Karlsruhe KADoNiS The Sequel to the “Bao et al.” neutron capture compilations.
12C(p,g)13N g III. Nuclear Reaction Rates 12C 13N Nuclear reactions
Nuclear and Radiation Physics, BAU, 1 st Semester, (Saed Dababneh). 1 Nuclear Reactions Categorization of Nuclear Reactions According to: bombarding.
Several nomenclatures are important: ● Nuclide: is any particular atomic nucleus with a specific atomic number Z and mass number A, it is equivalently.
Joint IAEA-ICTP Workshop on Nuclear Reaction Data for Advanced Reactor Technologies Student’s presentation Calculation of correction factors for neutron.
Jag Tuli NSDD, Vienna, 4/2015 ENSDF Policies 4/15 Jagdish Tuli* National Nuclear Data Center Brookhaven National Laboratory * Brookhaven.
Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 MACS and Astrophysical Reaction Rates from.
Egyptian Atomic Energy Authority-Egypt Second Research Reactor ETRR-2
1 CN formation cross section in nucleon induced reactions on 238 U Efrem Soukhovitski, JINER Frank Dietrich, LLNL Harm Wienke, Belgonucleaire Roberto Capote,
Status and needs of activation data for fusion Robin Forrest 1 and Jura Kopecky 2 1 Euratom/UKAEA Fusion Association Culham Science Centre, UK 2 JUKO Research,
Futoshi Minato JAEA Nuclear Data Center, Tokai Theoretical calculations of beta-delayed neutrons and sensitivity analyses 1.
Coupled-Channel Computation of Direct Neutron Capture and (d,p) reactions on Non- Spherical Nuclei Goran Arbanas (ORNL) Ian J. Thompson (LLNL) with Filomena.
TOTAL CROSS-SECTION MEASUREMENTS AND RESONANCE PARAMETER ANNYLISIS OF 169 TM BELOW 100 EV ICTP, Trieste, Italy 2010/05/14 Presentation in the Workshop.
Α - capture reactions using the 4π γ-summing technique Α. Lagoyannis Institute of Nuclear Physics, N.C.S.R. “Demokritos”
A=193 Mass Chain evaluation: A summary IAEA-ICTP Workshop on Nuclear Structure and Decay Data: Theory and Evaluation, Trieste, Italy November
UKRNDC Activity on Nuclear Data Support to Meet the Requirements Connected with Fundamental Science and Applications Olena Gritzay, Oleksandr Kalchenko.
1 Low Neutron Energy Cross Sections of the Hafnium Isotopes G. Noguère, A. Courcelle, J.M. Palau, O. Litaize CEA/DEN Cadarache, France P. Siegler JRC/IRMM.
Measurement of Neutron Total Cross Sections of Natural Hafnium and Tantalum at Pohang Neutron Facility Course Title: Experimental Method and Data Process.
Anti-neutrinos Spectra from Nuclear Reactors Alejandro Sonzogni National Nuclear Data Center.
V. Avrigeanu - Workshop on Activation Data (EAF-2005), Prague, June 7-9, Progress Report on Theoretical Tools and Calculations of Cross Sections.
Lawrence Livermore National Laboratory PREPRO Accomplishments Dermott “Red” Cullen Presented at the Nuclear Criticality Safety Program Technical Conference.
Status of the Evaluated Gamma-ray Activation File (EGAF) Richard B. Firestone Lawrence Berkeley National Laboratory Berkeley, CA
1 Roberto Capote, IAEA Nuclear Data Section Web: IAEA IAEA HQ, Vienna,
Forschungszentrum Karlsruhe in der Helmholz-Gemeinschaft Karlsruhe Institute of Technology Nuclear Data Library for Advanced Systems – Fusion Devices (FENDL-3)
Walid DRIDI, CEA/Saclay n_TOF Collaboration Meeting, Paris December 4-5, 2006 DAPNIA Neutron capture cross section of 234 U Walid DRIDI CEA/Saclay for.
International Atomic Energy Agency Nuclear Data for the Production of Therapeutic Radioisotopes: Background, Objectives and Expected Outputs 1 st RCM,
Update of uncertainty file in the EAF project J. Kopecky 1 and R.A. Forrest 2 1 JUKO Research, the Netherlands 2 EURATOM/UKAEA Association, Culham, UK.
TENDL for FENDL Arjan Koning NRG Petten, The Netherlands FENDL-3 meeting December 6-9, 2011, IAEA, Vienna.
LLNL-PRES This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under contract DE-AC52-07NA27344.
Cross-sections of Neutron Threshold Reactions Studied by Activation Method Nuclear Physics Institute, Academy of Sciences of Czech Republic Department.
Alejandro SonzogniNSDD 2007 Decay Data Library In ENDF/B-VII Alejandro Sonzogni National Nuclear Data Center Brookhaven National Laboratory
Filling up FENDL with an all-in-one nuclear data evaluation and validation system around TALYS Arjan Koning NRG Petten, The Netherlands FENDL-3 meeting.
NUCLEAR LEVEL DENSITIES NEAR Z=50 FROM NEUTRON EVAPORATION SPECTRA IN (p,n) REACTION B.V.Zhuravlev, A.A.Lychagin, N.N.Titarenko State Scientific Center.
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority EAF-2010 – the best of a generation Jean-Christophe Sublet, Lee Packer Euratom/CCFE.
6-1 Lesson 6 Objectives Beginning Chapter 2: Energy Beginning Chapter 2: Energy Derivation of Multigroup Energy treatment Derivation of Multigroup Energy.
1 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org NUCLEAR.
Nuclear Reactors, BAU, 1st Semester, (Saed Dababneh). 1 Neutron Attenuation (revisited) Recall  t = N  t Probability per unit path length.
1 Segrè Lost … ! Nuclear Fission How much is recoverable? How much is recoverable? What about capture gammas? (produced by -1 neutrons) What about capture.
Institute for Reference Materials and Measurements (IRMM) Geel, Belgium CRP Th - U, Vienna December 2004.
Santa Tecla, 2-9 October 2005Marita Mosconi,FZK1 Re/Os cosmochronometer: measurements of relevant Os cross sections Marita Mosconi 1, Alberto Mengoni 2,
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Modern , d, p, n-Induced Activation Transmutation Systems EURATOM/CCFE.
Faddeev Calculation for Neutron-Rich Nuclei Eizo Uzu (Tokyo Univ. of Science) Collaborators Masahiro Yamaguchi (RCNP) Hiroyuki Kamada (Kyusyu Inst. Tech.)
Data Needs in Nuclear Astrophysics, Basel, June 23-25, 2006 Nuclear Astrophysics Resources of the National Nuclear Data Center B. Pritychenko*, M.W. Herman,
Pavel Oblozinsky NSDD’07, St. Petersburg June 11-15, 2007 ENDF/B-VII.0 Library and Use of ENSDF Pavel Oblozinsky National Nuclear Data Center Brookhaven.
Final RCM on Therapeutic Radionuclides, IAEA, May/June Production cross sections for (n  reactions on 88 Sr, 102 Pd, 124 Xe, 130 Te, 152 Sm,
EGAF Status 2015 Richard B. Firestone Lawrence Berkeley National Laboratory and the University of California, Berkeley, 94720, USA 21 st Technical Meeting.
Cross-section data for accelerator-produced therapeutic radioisotopes: Progress report on experiments and data evaluations by the ATOMKI group ( )
Non-equilibrium Antineutrino spectrum from a Nuclear reactor We consider the evolution of the reactor antineutrino energy spectrum during the periods of.
1 G. Cambi, D.G. Cepraga, M. Frisoni Enea & Bologna University Team OSIRIS neutronic and activation simulation with Scalenea-ANITA in support of PACTITER/CORELE.
1 Cross sections of neutron reactions in S-Cl-Ar region in the s-process of nucleosynthesis C. Oprea 1, P. J. Szalanski 2, A. Ioan 1, P. M. Potlog 3 1Frank.
Ciemat Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas D. Cano-Ott, 6 th Geant4 Space Users Workshop Evaluated neutron cross section.
Zirconium capture measurements:
Investigation of the proton-induced reactions on natural molybdenum.
1. Nuclear Data Prof. Dr. A.J. (Arjan) Koning1,2
Beginning Chapter 2: Energy Derivation of Multigroup Energy treatment
3. The optical model Prof. Dr. A.J. (Arjan) Koning1,2
4. Level densities Prof. Dr. A.J. (Arjan) Koning1,2
Data improvements Request for Isotope Production at the Missouri University Research Reactor Facility Need gamma production spectrum for incident neutron.
Resonance Reactions HW 34 In the 19F(p,) reaction:
Nuclear Data for Reactor Fluxes
TALYS exercises I Arjan Koning Nuclear Data Section, NAPC
The TALYS nuclear model code II
Presentation transcript:

Applied Nuclear Physics Group The final meeting of IAEA CRP – 6. 2 Calculation and Evaluation of (n,  ) Cross Sections for Producing 32 P, 105 Rh, 131 I and 192 Ir H.D. Choi and S.K. Kim 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, 105 Rh, 131 I, 192 Ir  Production : 31 P(n,  ) 32 P, 104 Ru(n,  ) 105 Ru, 130 Te(n,  ) 131 Te, 191 Ir(n,  ) 192 Ir  Nuclear structure and decay data : ENSDF  Experimental data : EXFOR  Isomeric states for two isotopes : 131g,m1 Te, 192g,m1,m2 Ir  Thermal and RR region : resonance parameters + NJOY  Unresolved R region : libraries (ENDF/B-VI or JENDL-3.3)  High energy region : TALYS calculation (default) (OMP + other parameters tuning)  Integral data production & validation

Applied Nuclear Physics Group 3 32 P Production  Decay scheme of 32 P

Applied Nuclear Physics Group 4 32 P Production  Thermal neutron capture cross section of 31 P. AuthorPublication Thermal (n,  ) cross section [b] Seren (46) Pomerance (15) Grimeland (2) Jozefowitz (8) Kappe (74) Ishikawa (1) Salama (12) Zeng (5) Sun (unpublished) (2) Evaluation (Mughabghab) (6) This workAveraged cross section0.172(4)

Applied Nuclear Physics Group 5  Thermal cross section : 172(4) mb  Resonance parameters : JENDL-3.3  Negative energy resonance parameter tuning : E R = keV,   = 2.07 eV (tuned)  High energy region : 545 keV – 20 MeV TALYS default calculation (local OMP)  Consistency & improvement achieved  EXFOR item (Macklin) at 30 keV : compilation error Derived integral cross section for T = 30 keV Maxwellian Data uncertainty input error 32 P Production

Applied Nuclear Physics Group 6 32 P Production  31 P(n,  ) 32 P reaction cross sections

Applied Nuclear Physics Group 7  Decay scheme of 105 Ru and 105 Rh 105 Rh Production

Applied Nuclear Physics Group 8  Decay data for 105 Ru, ground and isomeric states of 105 Rh 105 Rh Production RadioisotopeHalf-lifeDecay modeMain radiation [keV] (branching ratio) 105 Ru4.44(2) hβ  (100%)  -rays (18.8%) (47.8%) … (17.5%) (47.3%) … 105m Rh45 sIT (100%)  -ray CE (20%) ce-K, (51.3%) ce-L, (23.1%) ce-M, (4.49%) 105 Rh35.36(6) hβ  (100%)  -rays 69.9 (19.7%) (75.0%, decay to ground state 105 Pd) … (5.1%) (19.1%) … IT : isomeric transition, CE : conversion electron, : average energy of  -rays.

Applied Nuclear Physics Group Rh Production  Thermal neutron cross section : two EXFOR items only both consistent  466(15) mb  Resonance parameters : Mughabghab +   = 0.14 eV (tuned) at E R = eV  Unresolved Resonance region (11 – 300 keV) : JENDL  Higher energy region (above 300 keV) : TALYS calculation normalization factor 1.9  14 MeV cross section = 3 mb Wagner(1980,latest) : 0.86(15) mb, average : 1.0(2) mb

Applied Nuclear Physics Group Rh Production  104 Ru (n,  ) 105 Ru reaction cross sections

Applied Nuclear Physics Group I production by 131g,m Te  -decay  Decay scheme of 131 Te and 131 I  Two final states of 131 Te 131m Te(30 hr) keV, 11/2 -, 77.8%  -decay, 22.2% IT 131g Te(25 m) g. s., 3/2 +, 100%  -decay

Applied Nuclear Physics Group 12  Decay data for ground and isomeric states of 131 Te and for 131 I RadioisotopeHalf-lifeDecay modeMain radiation [keV] (branching ratio) 131m Te30(2) h β  (77.8%) IT(22.2%)  -ray CE (0.85%) ce-K, (14.4%) ce-L, (5.44%) … 131g Te25.0(1) mβ  (100%)  -rays (9.96%) (21.7%) (59.3%) … (68.8%) (18.2%) … 131 I (11) dβ  (100%)  -rays 96.6 (7.3%) 192 (90%) … (82%) 637 (7.2%) … IT : isomeric transition, CE : conversion electron, : average energy of  -rays. 131 I Production

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

Applied Nuclear Physics Group I Production  Isomeric ratios for thermal neutron capture cross section of 130 Te AuthorPublication Isomeric ratios for thermal neutron capture δ 1 (= σ g /σ m )δ 2 (= σ m /σ g+m ) Seren Sehgal Mangal Namboodiri (3) Bondarenko (5) Reifarth (5) Tomandl-I (2) Tomandl-II (4) Evaluation (Mughabghab) (4) This studyAverage (3)

Applied Nuclear Physics Group 15 AuthorPublication Thermal neutron capture cross section [mb] σ0σ0 σ0gσ0g σ0mσ0m Seren (44)222(44) < 8(3) Pomerance (250) Sehgal (61)270(60)40(10) Mangal (24) Honzatko (20) Tomandl (13) Tomandl (20) Evaluation (Mughabghab) (61)270(60)20(10) This study Averaged cross section 204(10)192(10)12(1) 131 I Production  Thermal neutron capture cross section of 130 Te

Applied Nuclear Physics Group I Production  Thermal neutron cross section : weighted ave. δ 2 and σ γ0 σ  0 = 204(10) mb, δ 2 (25.3 meV) = 0.058(3)  Resonance parameters : JENDL   = 0.06 eV at E R = eV  Higher energy region (31 keV – 20 MeV) : TALYS calculation Fit to σ tot (E), σ  g+m (E), σ  g (E) by fine tuning OMPs, variation of target nucleus level density parameters, etc.  EXFOR entry (Dovbenko) for σ  g (E) : unit in mb (2 nd CRP)  Improve TALYS prediction for σ tot (E) around 1 MeV  Little improve for σ inel (E) and σ  (E)

Applied Nuclear Physics Group I Production  A fit to 130 Te+n total reaction cross section  tot (E) A fit (continuous line) Default TALYS result (dash dotted) Fit without normalization (dotted) EXFOR data (symbol).

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

Applied Nuclear Physics Group I Production  130 Te+n reaction channels cross sections (1 keV - 20 MeV)

Applied Nuclear Physics Group I Production  Energy variation of optical model potential depths Other parameters : fixed during the fit (a= fm, r= 1.22 fm, etc). Final OMPs within 2% change from global OMPs

Applied Nuclear Physics Group I Production  Branching ratios for 130 Te(n,  ) 131 Te

Applied Nuclear Physics Group Ir Production  Decay scheme of 192 Ir 1) Odd-odd tri-axially deformed nucleus 192 Ir : isomeric triplet 2) Decay and structure properties for g.s. and 1 st isomeric state : definite 3) 2 nd isomeric state : long-lived isomer First discovery (1959) One(+1?) measurement : discoverer Two measurements on half-life Latest measurement (1991) : theoretical discussion only Spin-parity, level energy and decay : arguments left More measurements needed !

Applied Nuclear Physics Group 23 RadioisotopeHalf-lifeDecay modeMain radiation [keV] (branching ratio) 192m2 Ir241(9) y IT (100%)  -ray CE (0.0974%) ce-L, 142 (74.6%) ce-M+, 153 (24.6%) ce-K, 79.1 (0.65%) 192m1 Ir1.45(5) m β - (0.0175%) IT ( %) CE  -ray ce-L, 43.3 (72.4%) ce-M, 53.5 (21%) ce-N+, 56.0 (6.5%) (0.003%) 192g Ir73.827(13)d β - (95.13%) EC (4.87%)  -rays 71.6 (5.6%) (41.4%) (48%) … (28.7%) (29.7%) (82.7%) (47.8%) … 192 Ir Production  Decay data for ground and isomeric states of 192 Ir

Applied Nuclear Physics Group Ir Production  Thermal neutron capture cross sections of 191 Ir Author Publication date Thermal neutron capture cross section [b] 00 0g0g   0 m1   0 m2 Seren (200)260(104) Harbottle ( ) Keisch (67) 300(30)610(60) Arino (300)300(50) Sims (25) Heft (13) Masyanov (3) Evaluation Mughabghab (10)309(30)645(32)0.16(7) NGATLAS EAF This work962(11)317(58)645(120)0.13(6)

Applied Nuclear Physics Group Ir Production  Thermal neutron cross section : weighted ave. σ γ0 isomeric cross sections : branch ratios by Keish(1963)  Resonance parameters : ENDF/B-VI +   = eV at E R = eV  Higher energy region (0.3 keV – 20 MeV) : TALYS calculation Fit to σ  (E) by fine tuning OMPs + normalization  No experimental set for σ tot (E), σ el (E)  TALYS predictions for σ γ g (E), σ γ m1 (E), σ γ m2 (E)

Applied Nuclear Physics Group Ir Production  191 Ir(n,  ) 192g,m1,m2 Ir cross sections (this work) Total capture cross section The resolved cross sections for ground state and two isomeric states are given separately.

Applied Nuclear Physics Group Ir Production  TALYS Predicting branching ratios of 191 Ir(n,  ) 192 Ir reaction

Applied Nuclear Physics Group Cu Production  67 Zn(n,p) 67 Cu cross sections (existing libraries + Qaim)

Applied Nuclear Physics Group Cu Production  64 Zn(n,p) 64 Cu cross sections (existing libraries + this CRP)

Applied Nuclear Physics Group 30 Validation and Integral Quantities  Integral quantities for 31 P(n,  ) 32 P cross section Sources σ  0 (2200 m/s) [b] Maxwellian(300 K ) [b] Resonance integral [b] Fast cross section [b] Fission Spectrum 14 MeV Mughabghab (evaluation) 0.172(6)0.085(10) ENDF/B-VI   JENDL   This Work0.172(4)   EXFOREXFOR Harris 1950~0.10 Macklin Hayodom (10)

Applied Nuclear Physics Group 31 Validation and Integral Quantities  Integral quantities for 104 Ru(n,  ) 105 Ru cross section Sources σ  0 (2200 m/s) [b] Maxwellian (300 K ) [b] Resonance integral [b] Fast cross section [b] Fission Spectrum 14 MeV Mughabghab (evaluation) 0.32(2)4.3(1) ENDF/B-VI   JENDL   This Work0.466(15)   EXFOREXFOR Lantz (4) Linden (3) Ricabarra Bereznai (25) Heft (65)

Applied Nuclear Physics Group 32 Validation and Integral Quantities  Integral quantities for 130 Te(n,  ) 131 Te cross section Sources σ  0 (2200 m/s) [b] Maxwellian (300 K ) [b] Resonance integral [b] Fast cross section [b] Fission Spectrum 14 MeV Mughabghab (evaluation of total) 0.290(61)0.46(5) ENDF/B-VI (total)   JENDL-3.3 (total)   This Work total0.204(10)   ground0.192(10)   isomeric0.012(1)   EXFOREXFOR Ricabarra (14) Browne (32) Linden (3)

Applied Nuclear Physics Group 33 Validation and Integral Quantities  Integral quantities for 191 Ir(n,  ) 192 Ir cross section Libraries σ  0 (2200 m/s)[b] Maxwellian (300 K ) [b] Resonance integral I 0 [b] Fast cross section [b] Fission14 MeV Mughabghab(evaluation)954(10)3500(100) ENDF/B-VI  JEFF  This Work Total962(11) ),5)  Ground317(58) )  Meta1645(120) ),6)  Meta20.13(6) ) 8.04   EXFOREXFOR Harris (230) 1) Sims (240) 1) Koehler (285) 2), 940(160) 3) Linden (382) 4) Heft (480) 1) Masyanov (70) 1)

Applied Nuclear Physics Group 34 Validation and Integral Quantities  Integral quantities for 191 Ir(n,  ) 192 Ir cross section 1) Lower limit of resonance integral = 0.5 eV, 2) Lower limit of resonance integral = 0.62 eV, 3) Value for the 1st isomeric state with lower integral limit 0.62 eV, 4) Lower limit of resonance integral = 0.55 eV, 5) I 0 tot (0.50eV) = 3558 b, I0tot(0.62eV) = 2940 b, 6) I 0 m1 (0.62eV) = 1969 b.

Applied Nuclear Physics Group 35 Validation and Integral Quantities  Integral quantities for 67 Zn(n,p) 67 Cu cross section Sources Spectrum averaged cross section [mb] FissionCf-252 *) Others Library Qaim calculation (STAPRE) [47] **) JEFF-3.1/A [21] **) JENDL-Act.[46] **) EvaluationCalamand 1974 [49]1.07(4) MeasurementHoribe 1989 [48]1.01(9) Brodskaja (7) Spahn 2004 [50]5.13(87)  ) *) Cf-252 neutron spectrum with effective temperature T=1.42 MeV and integration limit from 1 keV to 20 MeV were used. **) 14 MeV neutron spectrum with the same integration limit was used.  ) 14 MeV d(Be) neutron spectrum.

Applied Nuclear Physics Group 36 Validation and Integral Quantities  Integral quantities for 64 Zn(n,p) 64 Cu cross section Sources Spectrum averaged cross section [mb] FissionCf-252 *) Others LibraryRNAL (Qaim adoption) **) JEF **) IRDF **) RRDF-2006 [51] **) EvaluationCalamand 1974 [49]31.0(23) Mannhart 1989 [53]40.47(75) Mannhart 2003 [54]40.59(67) MeasurementCohen 2005 [52]37.4(14) Kobayashi (18) Benabdallah (15) Kobayashi (17) Spahn 2004 [50]132(25)  )

Applied Nuclear Physics Group 37 Much thanks to Dr. Dad. Jean Sublet, Arjan Koning, and Everyone !!!