1 n_TOF data-analysis workshop CERN, Geneva, 25-27 February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org NUCLEAR.

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1 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org NUCLEAR DATA EVALUATION NEEDS: Impact of n_TOF measurements on nuclear applications Roberto Capote and Naohiko Otsuka Nuclear Data Section International Atomic Energy Agency

2 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org OUTLINE  Nuclear data evaluation in a nutshell  Overview of n_TOF results and their impact  Summary and outlook

3 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org Nuclear Data Evaluation From D. Neudecker, S. Gundacker, H. Leeb et al., ND2010, Jeju Isl., Korea

4 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org Definition of (ND) Evaluation A properly weighted combination (usually by GLSQ fit) of selected experimental data (and nuclear reaction modelling results). Bayesian approaches:  “Non-model” GLSQ fit: neutron standards (STD) IAEA STDs:  R-matrix (non-model fit) – RR evaluations  Model prior + GLSQ fit Experimental nuclear physicists Theoreticians and reaction modellers Evaluators

5 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org Neutron standards: Files include additional energy range beyond STD !! ENDF/B-VII.1 almost = STD JEFF-3.2  IAEA STD JENDL-4.0  IAEA STD www-nds.iaea.org/standards/ Nuclear Data Sheets 110 (2009)

6 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org Evaluated 238 U(n,f) vs. IAEA STD cross section

7 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org Evaluated 238 U(n,f) vs. IAEA STD cross section raw EXFOR ratio data U8/U5, U5 std

8 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org Nuclear reaction data evaluation  Resonance energy range (  << D)  Fast neutron range (  >> D stat models) keV for actinide, MeV for Ni, Fe, Cr,…  Unresolved resonance range (in between) (self-shielding)

9 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org Evaluation – resonance range (RR)  Theoretical predictions not possible yet  Resonance parameters must be obtained from fitting ALL AVAILABLE experimental data  Modern resonance fitting codes produce “best fit” parameters as well as their covariances (e.g. SAMMY, REFIT, CONRAD, etc.)

10 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org Evaluation – resonance range - example

11 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org Depends on resolution function RPs, background, … To be combined with transmission...

12 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org n_TOF data in EXFOR & impact on applications

13 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org A very optimistic point of view… Data published & at EXFOR extracted from Lederer’s pres.

14 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org What do engineers need? I need cross sections … Usually evaluated cross sections from ENDF-B,JEFF,JENDL,… Back to the real world

15 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org What n_TOF collaboration usually provided? Here you are … It is all described in my article in the Phys.Rev. C ! Or even worse … Please use my Resonance Parameters Impossible to evaluate data in the RR !!! 

16 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org n_TOF Published Fission Data in EXFOR (www-nds.iaea.org/nrdc/n_tof) Target1 st authorReferenceEXFORRP<σ><σ>σ*σ*Y PbnatD. TarrioPRC83(2011) ,8,X-- 209Bi5,8,X-- 233UM. CalvianiPRC80(2009) XX F. BelloniEPJA47(2011) ,X 234UC. ParadelaPRC82(2010) XX D. KaradimosPRC89(2014) UR. SarmentoPRC84(2011) XX 237NpC. ParadelaPRC82(2010) X5,X 241AmF. BelloniEPJA49(2013) ,X 243AmF. BelloniEPJA47(2011) ,X 245CmM. CalvianiPRC85(2012) X U5/U8C. ParadelaPRC91(2015)024602in comp.X-- * 5: ratio to 235U(n,f) cross section; 8: ratio to 238U(n,f) cross section

17 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org P.M. Milazzo et al, AIP 1265 (2010) 477 How evaluators can improve evaluations with no data? 233 U(n,f)

18 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org n_TOF Published Capture Data in EXFOR (1/4) ( #Target1 st authorReferenceEXFORRPMACS<σ><σ>σY 124MgC. MassimiPRC85(2012) XX 225MgXX 326MgXX 458NiP. ŽugecPRC89(2014) XXXX 562NiC. LedererPRC89(2014) XX 663NiXXX 790ZrG. TaglientePRC77(2008) XX 8PRC87(2013) X 991ZrPRC78(2008) XX 10PRC87(2013) X 1192ZrPRC81(2010) XX 12PRC87(2013) X MACS – astrophysics, Yield (Y) – nuclear energy

19 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org n_TOF Published Capture Data in EXFOR (2/4) ( #Target1 st authorReferenceEXFORRPMACS<σ><σ>σY 1393ZrG. TaglientePRC87(2013) XX 1494ZrPRC84(2011) XX 15PRC87(2013) X 1696ZrPRC84(2011) XX 17PRC87(2013) X 18139LaR. TerlizziPRC75(2007) XX 19151SmS. MarronePRC73(2006) XXX OsM. MosconiPRC82(2010) XX 21 K. FujiiPRC82(2010) X OsM. MosconiPRC82(2010) XX 23 K. FujiiPRC82(2010) X LaR. TerlizziPRC75(2007) XX MACS – astrophysics, Yield (Y) – nuclear energy

20 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org n_TOF Published Capture Data in EXFOR (3/4) ( #Target1 st authorReferenceEXFORRPMACS<σ><σ>σY 25188OsM. MosconiPRC82(2010) XX 26K. FujiiPRC82(2010) X 27197AuC. MassimiPRC81(2010) X 28C. LedererPRC83(2011) XXX 29204PbC. Domingo-PRC75(2007) XXX 30206PbPRC76(2007) XX 31207PbPRC74(2006) XX BiPRC74(2006) XX ThG. AertsPRC73(2006) X* 34 F. GunsingPRC85(2012) X NpC. GuerreroPRC85(2012) XX AmK. FravalPRC89(2014) X MACS – astrophysics, Yield (Y) – nuclear energy

21 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org n_TOF Published Capture Data in EXFOR (4/4) ( #Target1 st authorReferenceEXFORRPMACS<σ><σ>σY 37243AmE. MendozaPRC90(2014) *XXXX MACS – astrophysics, Yield (Y) – nuclear energy * in compilation Suggestions:  No need to compile into EXFOR by n_TOF !  No need to centralize submission (data lost?)  First author should submit (as approved by PC): 1) the paper (to the journal) 2) the yield and other data to the IAEA

22 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org How to submit the data to the IAEA? Complicated??

23 n_TOF data-analysis workshop CERN, Geneva, February 2015 Roberto Capote, IAEA Nuclear Data Section www-nds.iaea.org TAKE HOME MESSAGE  Job is not finished till ALL data are submitted Recommendation: submit the yield to the IAEA with the paper to the journal Both for capture and fission experiments:  Capture/Fission yields (= input for SAMMY)  Cross sections (preferably what is measured = ratio to STD) Only exception: (n,f) or (ng) data above the Resonance Range (in this case only cross sections are needed)  n_TOF impact on (n,g) evaluations low  (02/15) Only 232 Th(n,g) capture yield used in IAEA (other) evaluation so far (adopted by..) !!! Situation is improving (2 new sets) but huge backlog needs to be sorted out  n_TOF provided excellent data on U5f/U8f to the IAEA STD group Ratios of other STD cross sections needed – e.g. Au(n,g)/U8(n,g),Li6t/10Ba