1. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 MACS and Astrophysical Reaction Rates from ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, ENDF/B-VI.8 Evaluated Neutron Libraries B. Pritychenko*, A. Sonzogni, S. Mughabghab National Nuclear Data Center Brookhaven National Laboratory * Email: pritychenko@bnl.gov Brookhaven Science Associates

2. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 2 Evaluated Neutron Libraries  Nuclear Data activities started at BNL in 1951 with neutron compilations  BNL-325 & Evaluated Nuclear Data File  ENDF: core nuclear reaction database containing evaluated (recommended) data from the ENDF/B-VII.0 library (also JEFF, JENDL, BROND, CENDL and ENDF/B-VI.8). It uses ENDF-6 format, covering all nuclides of practical relevance (393 in total) for neutrons from 10 -5 eV up to 20 MeV  ENDF/B-VII.0 library was released on December 15, 2006

3. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 3 ENDF/B-VII.0 Astrophysics Features  393 Neutron Evaluations in ENDF/B-VII.0 vs. 337 in JENDL-3.3 released in 2002  251 out of 286 nuclides (87.7%) from solar nuclide abundances paper by E. Anders & N. Grevesse, Geochim. Cosmochin. Acta 53 (1989) 197  390 (n,  ) cross sections, no cross sections for 3 H, 4 He, 7 Be  Good for Maxwellian-averaged cross sections (s-process nuclei), astrophysical reaction rates

4. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 4 Project Motivation  ENDF data in eV – MeV regions are utilized by nuclear industry, fussion, national security applications  keV region data for nuclear astrophysics  Calculate 4 major neutron libraries under the same conditions  Connection between ENDF & astrophysics  Sigma: New ENDF Web interface

5. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 5 MACS & Reaction Rates I Nuclear astrophysics s-process calculations require Maxwellian average neutron capture cross sections. Maxwellian cross section in nuclear astrophysics region are not more than 10% off from (n,  ) cross sections

6. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 6 MACS & Reaction Rates II  Nakagawa et al., ADNDT 91 (2005) 77  Maxwellian-averaged cross section, [b]  Astrophysical reaction rate, [cm 3 /s]

7. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 7 Java Implementation  Pointwise* ENDF data at 300K in Sigma DB (0K pointwise is in progress)  AME2003 in  -decay database  Java 1.5 Simpson summation of pointwise data splitted into 2 slices, slice width < 10 keV for 26 neutron energy values: kT = 0.001 - 1 MeV  Evaluated neutron data for all major libraries: ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, ENDF/B- VI.8 were processed on Windows desktop in 4 - 5 h * It refers to conversion of resonance parameters into cross sections and to Doppler broadening them by taking into account neutron velocities at room temperature. Applies only to the neutron sublibrary in the resonance region.

8. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 8 Numeric Integration  Lower & Upper Riemann (Rectangular), Trapezoidal, Midpoint, Recursive (Trapezoidal Power Of Two, Romberg, Simpson )  Simpson integration is prefferable  Sigma pointwise libraries were linearized within 0.1%:  m = (  1 +  2 )/2

9. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 9 Maxwellian Cross Sections  Java numerical integration performs better than INTER ENDF utility code  Simple trapezoidal MACS for JENDL-3.3 are within 2-5% from T. Nakagawa et al., ADNDT 91 (2005) 77 calculations based  Simpson numerical integration + division of each slice into 2 + slice width < 10 keV agrees with Nakagawa et al. within 1%  Hybrid (analytical + numerical) integration  Bao et al.

10. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 10 MACS comparison for 151 Sm(n,  )  U. Abbondanno et al., PRL 93,161103 (2004)  K. Wisshak et al., PRC 73, 015802 (2006)  Simpson MACS (mb): Energy, keV10152025304050 PRL (2004)3100 (160) PRC (2006)6082470439253407303125102158 ENDF/B-VII.0 (2006) 6060460037913262287923531999 JEFF-3.1 (2005)6658507941833586315325572161 JENDL-3.3 (2002) 3987308625832249200516631430 ENDF/B-VI.8 (2001) 5463411833802904256721171826

11. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 11 Reaction Rates  Reaction rates for four major libraries have been calculated  Neutron cross sections (30 keV) x Solar abundances (relative to Si = 10 6 )   N ratio: JENDL-3.3: 122 Te: 123 Te: 124 Te => 1:0.94:1.03 ENDF/B-VII.0: 122 Te: 123 Te: 124 Te =>1:1.18:0.9  Covariances => Uncertainties

12. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 12 Conclusion & Outlook  (n,  ) Maxwellian cross sections and reaction rates have been calculated for four major libraries: ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, ENDF/B-VI.8  Results were compared with:  Calculations T. Nakagawa et al. ADNDT 91 (2005) 77  Bao et al.  ENDF utility code INTER  Neutron cross sections x Solar system abundances  (n,p), (n,  ), (n,f), (n,2n), (n,t+2  ) reactions will follow  Results will be loaded into Sigma database (Sigma Demonstration for Trento meeting)  Future covariances will produce errors for MACS/Reaction Rates

13. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 13 MACS comparison for 19 F(n,  )  E. Uberseder et al., Phys. Rev. C75,035801 (2007), 44% lower than previous result  Simpson MACS (mb) for LA+CNDC+ORNL: Energy, keV10152025304050 PRC75 (2007) 4.14.54.23.7+-0.13.22.52.0 ENDF/B- VII.0 (2006) 5.46.15.65.04.43.42.7 JEFF-3.1 (2005) 5.46.15.65.04.43.42.7 JENDL-3.3 (2002) 6.57.47.16.45.74.63.8 ENDF/B- VI.8 (2001) 9.610.59.48.16.95.24.0

14. Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 14 Email from Nakagawa Dear Boris, Thank you for your e-mail. Concerning nuclear masses, we used values given in head records of JENDL-3.3. I think small discrepancies between our results and yours might be caused by integration methods. In our calculation for adjacent two cross-section data points, a table of Sig(E)*E*exp(-E/kT) was created at fine energy mesh by using the dividing method originally used in RESEND code. Then integration was made by subroutine ECSI taken from ENDF/B utility codes. Best regards, Tsuneo