Presentation for the CIELO Meeting of the NEA 9-11 May 2016 Paris, France. The Chinese work on 56 Fe

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1 The Chinese work on 56 Fe Jing QIAN, Zhigang GE, Tingjin LIU, Hanlin LU, Xichao RUAN Guochang CHEN,Huanyu Huanyu ZHANG,Yangbo NIE China Nuclear Data Center(CNDC) China Institute of Atomic Energy(CIAE) P.O.Box ,Beijing , P.R.China

2 Evaluation of all cross sections in fast range Integral Benchmarking Summary

3 Evaluation of all cross sections in fast range Experimental data evaluation Theoretical calculation by UNF series code Compilation of evaluated data(checking, CRECTJ6) New Resonance range evaluation (adopted d from CIELO-Iron-beta1) I were merged with the new fast-neutron evaluation ACE file processed by NJOY (by M.Herman and Ramon) Comparison with other evaluated data (CIELO-Iron-beta1 B7.1 JEFF3.2 RSF JENDL4.0 CENDL-3.1)

4 Theoretical calculation result by code UNF UNF series Code APMN06 UNF2008 NDDX,TT DWUCK output A set of suitable OMP were given Calculate the contribution from direct part(dwba) Out put ENDF file DAE and DE were polted Level density parameters and pair correction: Level density parameters OMP V 0 Presentation for the CIELO Meeting of Uthe 2 NEA V r r V r s V r v V α r W α s W α v W U SO U r so U a so β param meters 1 so level Energy Jπ β (n,γ) (n,n ) (n,p) (n,α) (n, 3 He) (n,d) (n,t) (n,2n) (n,n α) (n,np) (n,3n) Pair correction

5 MF MT Data Source ENDF/B-VII.1 4 Cielo Iron-beta1 A resonance evaluation was performed at ORNL (Leal) from 1.0e-5 ev to 2 MeV using transmission data taken at the LINAC (Danon) and inelastic cross section measurements done GEEL (Plompen). Adopt GEEL2014 Exp Data(~6MeV)+Fit Nelson2004Exp Data(6~20MeV) 3,51 Adopt GEEL2014 Exp Data(~4.577MeV) + Theoretical calculated result(unf) (4.577~20MeV) 3,52~88 Theoretical calculated result(unf) 3,91 (3,4)-(3,51:88) 16 Fit Exp Data and ENDF/B-VII ENDF/B-VII.1 102, 104,105, Theoretical calculated result(unf) 106,107 3 (3,3)=(3,102)+(3,4)+(3,16)+(3,103)+(3,104)+(3,105)+(3,106)+(3,107) 2 (3,2)=(3,1)-(3,3) 3) 4 2 Theoretical calculated result(unf) 5,6 Theoretical calculated result(unf)

6 (n,tot) (n,inl) (n,2n) (b) Section (n,p) (n,α) Cross (n,gamma)

7 The experimental data of r-ray production cross sections were corrected and converted to the inelastic cross section. Presentation for the CIELO Meeting of the NEA

8 Adopt GEEL experimental data below 6MeV and fit Nelson s data up to 20MeV

9

10

11 Exp.data given by GEEL fromthresholdto45mev to 4.5 Presentation for the CIELO Meeting of the NEA

12 Adopt GEEL Exp Data(~4.577MeV) + Theoretical calculated result(unf) (4.577~20MeV)

13 MF MT DataPresentation Source for the CIELO Meeting of the NEA Cielo Iron-beta1 A resonance evaluation was performed at ORNL (Leal) from 1.0e-5 ev to 2 MeV using transmission data taken at the LINAC (Danon) and inelastic cross section measurements done GEEL (Plompen). 1 ENDF/B-VII.1 4 Adopt GEEL2014 Exp Data(~6MeV)+Fit Nelson2004Exp Data(6~20MeV) 3,51 Fit GEEL2014 Exp Data(~4.577MeV) + Theoretical calculated result(unf) (4.577~20MeV) 3,52~88 Theoretical calculated result(unf) 3,91 16 Fit Exp Data and ENDF/B-VII ENDF/B-VII.1 102, 104,105, Theoretical calculated result(unf) 106,107 (3,4)-(3,51:88) (3,5 The continuous inelastic cross section was given by subtracting the all discrete levels from total inelastic cross section 3 (3,3)=(3,102)+(3,4)+(3,16)+(3,103)+(3,104)+(3,105)+(3,106)+(3,107) 2 (3,2)=(3,1)-(3,3) 4 2 Theoretical calculated result(unf) 5,6 Theoretical calculated result(unf)

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15 56 Fe(n,p) The (n, p) cross section is a secondary standard cross section, there are no substantial difference for all evaluated libraries, and adopt evaluated data from ENDF/B-7.1 directly.

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17 (n,non) (n,el) (n,2n) (n,p) (n,α)

18 MF MT Data Source Cielo Iron-beta1 A resonance evaluation was performed at ORNL (Leal) from 1.0e-5 ev to 2 MeV using transmission data taken at the LINAC (Danon) and inelastic cross section measurements done GEEL (Plompen). 1 ENDF/B-VII.1 4 Fit GEEL2014 Exp Data(~6MeV)+Nelson2004Exp Data(6~20MeV) 3,51 Fit GEEL2014 Exp Data(~4.577MeV) + Theoretical calculated result(unf) (4.577~20MeV) 3,52~88 Theoretical calculated result(unf) 3,91 (3,4)-(3,51:88) 16 Fit Exp Data and ENDF/B-VII ENDF/B-VII.1 102, 104,105, Theoretical calculated result(unf) 106,107 3 (3,3)=(3,102)+(3,4)+(3,16)+(3,103)+(3,104)+(3,105)+(3,106)+(3,107) 2 (3,2)=(3,1)-(3,3) 3) 4 2 Theoretical calculated result(unf) 5,6 Theoretical calculated result(unf)

19

20 Elastic scattering angular distribution

21 The relationship between each reactions Presentation for the CIELO Meeting of the NEA This work is reasonable and (n,tot) in good agreement with evaluated experimental data (n,el) (n,non) (n,inl) (n,2n) (n,p) (n,α)

22 MF MT Data Source ENDF/B-VII.1 4 Cielo Iron-beta1 A resonance evaluation was performed at ORNL (Leal) from 1.0e-5 ev to 2 MeV using transmission data taken at the LINAC (Danon) and inelastic cross section measurements done GEEL (Plompen). Adopt GEEL2014 Exp Data(~6MeV)+ Fit Nelson2004Exp Data(6~20MeV) 3,51 Fit GEEL2014 Exp Data(~4.577MeV) + Theoretical calculated result(unf) (4.577~20MeV) 3,52~88 Theoretical calculated result(unf) 3,91 (3,4)-(3,51:88) 16 Fit Exp Data and ENDF/B-VII ENDF/B-VII.1 102, 104,105, Theoretical calculated result(unf) 106,107 3 (3,3)=(3,102)+(3,4)+(3,16)+(3,103)+(3,104)+(3,105)+(3,106)+(3,107) 2 (3,2)=(3,1)-(3,3) 3) 4 2 Theoretical calculated result(unf) 5,6 Theoretical calculated result(unf)

23 0 Fe(n,xn) DE 14.1MeV Presentation for the CIELO Meeting of the NEA In good agreement with experimental data, especially in the energy region where the neutrons come from inelastic scattering of discrete levels. The results of (n, n ), (n, p), (n, 2n) and (n, α) cross sections are reasonable.

24 0 Fe(n,xn) DE 14.1MeV Presentation for the CIELO Meeting of the NEA This work is more close to the experimental p data in the energy region 4-7 MeV than others.

25 0 Fe(n,xn) DE 14.1MeV Presentation for the CIELO Meeting of the NEA C i t t ith RSF d JEFF b tt th Consistent with RSF and JEFF, better than CENDL-3.1

26

27

28 Evaluation of all cross sections in fast range Integral Benchmarking Summary

29 Integral Benchmarking Presentation for the CIELO Meeting of the NEA (By Huanyu Zhang, CNDC, China) The new evaluated Fe-56 of this work were tested t with shielding and criticality benchmarks by using MCNP5. Integral experiments Lawrence Livermore National libratory pulse sphere experiment Neutron leakage spectra measurement in CIAE 168 critical benchmarks was selected from ICSBEP (Fe-56 collision weight simulated by MCNP > 0.1). The evaluated Fe-56 CNDC (this work) CIELO(Cielo-beta1) Comparison of benchmarking results Other nuclides except Fe-56 in the benchmarks are from ENDF/B-VII.1.

30 Comparison of Shielding Benchmarks Result Presentation for the CIELO Meeting of the NEA 14.1MeV (thiswork) The new evaluated inelastic scattering cross sections improve the leakage neutron spectra above 7 MeV.

31 Comparison of Shielding Benchmarks Result (2) Presentation for the CIELO Meeting of the NEA 14.1MeV (thiswork) But lower than experiments, CIELO and ENDF/B-VII.1 in the range of 9-10MeV

32 Comparison of Shielding Benchmarks Result (3) 14.1MeV (thiswork)

33 Neutron leakage spectra measurement induced by 14 MeV neutrons (By Yangbo Nie, CIAE, China) Slab sample 10*10*5 cm D-T neutron source Neutron detector

34 The experimental data is a preliminary result which is consistent with evaluated data. Our new evaluation will be compared with data later.

35 Integral Benchmarking Presentation for the CIELO Meeting of the NEA (By Huanyu Zhang, CNDC, China) The new evaluated Fe-56 of this work were tested t with shielding and criticality benchmarks by using MCNP5. Integral experiments Lawrence Livermore National libratory pulse sphere experiment Neutron leakage spectra measurement in CIAE 168 critical benchmarks was selected from ICSBEP (Fe-56 collision weight simulated by MCNP > 0.1). The evaluated Fe-56 CNDC (this work) CIELO(Cielo-beta1) ) Comparison of benchmarking results Other nuclides except Fe-56 in the benchmarks are from ENDF/B-VII.1.

36 Comparison of Critical Benchmarks Result ENDF/B-VII.1 JENDL-4.0 CENDL-3.1 CIELO CNDC Delta k 10 3 eff (1 pcm) HMF HMI HMT HST ICI ICT IMF LCT LST Benchmark MMF PMF PST

37 Highly Enriched Uranium System HEU-MET-FAST C/E K-eff exp ENDF/B VII.1 JENDL CENDL 3.1 CIELO CNDC E+03 1.E+04 1.E+05 1.E+06 EALF (ev) HMF021_01,HMF024_01,HMF034_03,HMF048_16,HMF048_17

38 C/E K-eff exp ENDF/B VII.1 JENDL 4.0 CENDL 3.1 CIELO CNDC HEU-MET-THERM HMT013_2 HMT013_ HMT015_ EALF (ev) HMT013_01,HMT013_02,HMT015_01

39 C/E K-ef ff exp ENDF/B VII.1 JENDL 4.0 CENDL 3.1 CIELO CNDC HEU-SOL-THERM HST016_ E-02 1.E-01 1.E+00 1.E+01 EALF (ev) HST004_03~06, HST006_09, HST016_01, HST016_02, HST019_01, HST019_02, HST019_03, HST020_05, HST038_15, HST049_01, HST049_09

40 Intermediate Enriched Uranium System IEU-COMP System C/E K-eff ICT05_4 exp ENDF/B VII.1 JENDL 4.0 CENDL 3.1 CIELO CNDC 1.E-02 1.E-01 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06 EALF (ev) ICF001_01,ICI001_02,ICI001_03,ICT002_01,ICT002_03,ICT002_05

41 Low Enriched Uranium System LEU-COMP-THERM exp ENDF/B VII.1 JENDL 4.0 CENDL 3.1 C/E K-eff CIELO CNDC EALF (ev) LCT018_01,LCT019_01~03,LCT020_01~07,LCT021_01,LCT022_01~06, LCT023_ 01~06,LCT024_ 01~02,LCT025_ 01~04,LCT026_ 01,LCT026_ 03, LCT026_05,LCT048_01

42 LEU-SOL-THERM Presentation for the CIELO Meeting of the NEA C/E exp ENDF/B VII.1 JENDL 4.0 CENDL 3.1 CIELO CNDC K-eff EALF (ev) LST004_01~07,LST016_01~07,LST017_01~06,LST018_01~06, LST019_01~05,LST020_01~0404 For LST system, the k eff bias against EALF is related to Fe-56. The new evaluated RRPs cause the slope of the bias get a litter large.

43 ZPPR-21 Assembles exp MIX-MET-FAST C/E K-eff ENDF/B VII.1 JENDL 4.0 CENDL 3.1 CIELO CNDC E E E E E E+05 EALF (ev) MMF011_01 ~04 It is sensitive to 56 Fe(n,inl) and (n,el) cross sections. The calculated results get worse or better than B71

44 1.01 exp Plutonium system PU-ME-FAST (Fe reflect) C/E K-eff ENDF/B VII.1 JENDL 4.0 CENDL 3.1 CIELO CNDC E E E E E E E E E+06 EALF (ev) PMF045_07,PMF045_06,PMF045_02,PMF015,PMF045_03,PMF028,PMF026,PMF032,PMF025

45 PU-SOL-THERM C/E K-eff exp ENDF/B VII.1 JENDL 4.0 CENDL 3.1 CIELO CNDC E E E E E E E E E E-01 EALF (ev) PST010_01~14,PST012_06~12,PST023_01~34

46 Evaluation of all cross sections in fast range Integral Benchmarking Summary

47 summary Evaluation of all cross sections from CNDC in fast range was finished. The result is in good agreement with evaluated experimental data. Energy spectra and double differential cross sections for neutron emission show the cross sections are reasonable. Integral Benchmarking shows the new evaluated inelastic scattering cross sections improve the leakage neutron spectra above 7 MeV. The results of CNDC show good agreements with those results from CIELO. But no significant ifi improvement was found in criticality benchmarks.

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