Status and future plan of JENDL. Osamu Iwamoto Nuclear Data Center Japan Atomic Energy Agency

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1 Status and future plan of JENDL Osamu Iwamoto Nuclear Data Center Japan Atomic Energy Agency 1

2 Introduction JENDL-4.0 was released in 2010 with improving fissionproduct, minor-actinide, and covariance. Present status: Special Purpose File Recently released: JENDL/PD-2016: new photonuclear reaction data file JENDL/AD-2017: activation c.s. file for decomissioning General Purpose File JENDL-5: developing next version of JENDL-4.0 2

3 JENDL Photonuclear Data File 2016 JENDL/PD-2016 Released in Dec H-2 (Z=1) to Lr-266 (Z=103): Cross section: photo-absorption, photo-fission, particle-production, residual-nuclide production Light particle emission spectrum (DDX) Incident energy: 1 MeV to 140 MeV. Standard version: 181 nuclides along the betastability line (based on experimental data) Expanded version: 2681 nuclides covering a wide range of unstable ones (mainly model calculations) 3

4 Proton number Nuclides in JENDL/PD (Standard) (Extended) 68 nuclides Neutron number 4

5 Cross section (mb) Evaluated data for O-16(g,n)O-15 Photon energy (MeV) 5

6 JENDL Activation Cross Section File for Nuclear Decommissioning 2017 (JENDL/AD-2017) Released in March 2018 For radioactive inventory evaluation on decommissioning of nuclear facilities neutron nuclear reactions (Fe-56 include proton induced reaction) 311 nuclides (to produce 221 RIs) The energy range up to 20 MeV. The pointwise data 0 K and K 6

7 New evaluation for C-13 Neutron capture cross section 7

8 Cross section (kb) Eu evaluation with measurement of J-PARC ANNRI 151 Eu(n,g) 152 Eu 8

9 Activity/clearance level (a.u.) Simple estimation of activitiy of concrete irradiated by BWR neutron spectrum Time after irradiation (year) 9

10 Topics of JENDL-5 Improve reliability and completeness for various applications Revise data of light nuclei, structural material, FP, actinide Include all stable isotopes More covariance data Add isomer production for activation evaluation New R-matrix code, AMUR Evaluation with new J-PARC data (mainly for MA) New simultaneous evaluation of fission cross section for major actinide New thermal neutron scattering law Include the data of charged particle induced reactions To be released hopefully in FY2021 (format GND?) 10

11 The first test version JENDL-5a1 JENDL-5a1 was created in 2018 Updated and newly evaluated elements in JENDL- 5a1 Ga, Zr, Nb, Tc, Ru, Sb, Te, I, Pr, Gd, Er, Ta, Re, Pt, Hg, Tl, U, Pu, Am New thermal scattering law Benchmark tests are in progress. 11

12 JENDL-5 Light nucleus evaluation New R-matrix code AMUR Preliminary evaluation of N-15, O-16, F-19 Covariance JENDL-4.0(=JENDL-3.3) covariance evaluation K.Shibata et al. JNST44.1(2007) GMA evaluation Uncertainty 12

13 Result of resonance analysis 15 N(n,tot), exp : Zeitnitz+ (1997) AMUR fit s th : ATLAS-2006 (n,n1) thr. Uncertainty of 15 N(n,tot) cross-sections Cov. 13

14 JENDL-5 Structural material Add isomer production data Update resonance parameters Above the resonance region model calculation with CCONE Covariance data will be evaluated CCONE + KALMAN 14

15 JENDL-5 Structural material Isomer productions are important as reactor dosimeter and neutron flux monitor. CCONE calculations simultaneously reproduce isomer and total cross sections. Cross Section (b) Ikeda+ (m.s.) 93 Wagner+ (m.s.) 88 Wagner+ (m.s.) 88 Gayther+ (m.s.) 81 Ryves+ (m.s.) 80 Taylor+ (m.s.) ENDF/B VIII.0 (m.s.) JEFF 3.3 (m.s.) JENDL 5a1 (m.s.) 93 Nb (n,n') Incident Neutron Energy (MeV) 94 Lashuk+ 92 Simakov+ 77 Kozur+ 74 Birjukov+ 73 Vanheerden+ 70 Goebel+ 63 Thomson 63 Glazkov JENDL 4.0 ENDF/B VIII.0 JEFF 3.3 JENDL 5a1 Cross Section (b) JENDL 4.0 ENDF/B VIII.0 JEFF 3.3 JENDL 5a1 93 Nb (n,2n) 11 Honusek+ (m.s.) 07 Mannhart+ (m.s.) 00 Kiraly+ (m.s.) 00 Fessler+ (m.s.) 99 Filatenkov+ (m.s.) Incident Neutron Energy (MeV) A. Ichihara, JNST 53,2049 (2016) JEFF 3.3 (m.s.) JENDL 5a1 (m.s.) 84 Lychagin+ 80 Frehaut+ 80 Prokopets 77 Veeser+ 77 Kozur+ 76 Holub+ 72 Mather+ 93 Ikeda+ (m.s.) 91 Molla+ (m.s.) 91 Smith+ (m.s.) 90 Santry+ (m.s.) 90 Kimura+ (m.s.) 15

16 JENDL-5 Fission products and medium heavy nuclides Objectives Updating old FP evaluations Providing activation cross sections for decommissioning of LWRs Evaluated nuclides Ga, Nb, Tc, Sb, Te, I, Er Ta, Pt, Hg, Tl Most of them have already published from JNST. Bi (preliminary) 16

17 Evaluated results for Te and I isotopes Te elastic scattering nat Te(n,n 0 ) K. Shibata, JNST 52, 490 (2015) K. Shibata, JNST 52, 1174 (2015) 17

18 Preliminary evaluation of Bi

19 JENDL-5 actinide evaluation Resonance analysis with new ANNRI measurements for MA. Create test files adopting CIELO evaluations of resolved resonance parameters of major actinides. Preliminary result of the fission cross section evaluation in fast neutron energy region for 6 isotopes of U and Pu. 19

20 Capture yield Transmission Am-241 resonance analysis with new measurement by ANNRI 20

21 Energy dependence of delayed neutron Summation calculation by energy dependent systematics of fission product yields F. Minato, JNST 55, 1054 (2019) 21

22 Thermal scattering data for light water Y. Abe et al., NIMA 735 (2014) (MD based approach) Total cross section Thermal scattering cross sections for water Cross Section (b/molecule) Zaitsev et al. (297 K) 91 Zaitsev et al. (303 K) 66 Russell et al. 61 Heinloth JENDL 4.0 (296 K) ENDF/B VIII.0 (293.6 K) JEFF 3.3 (293.6 K) JENDL 5a (300K ) Incident Neutron Energy (ev) *JENDL-4.0, ENDF/B-VIII.0, JEFF-3.3 includes the contribution from H only. 22

23 Deuteron induced reaction: DEURACS Elastic scattering Inelastic breakup n + A : n : p Absorption d + A :CCONE :DEURACS Inelastic breakup p + A Elastic breakup 23

24 Neutron emission 12 (DDXs) 12 (TTYs) 0 o (x1) 3.5 o (x1) 15 o (x10-2 ) 9 o (x10-2 ) S. Nakayama et al., RPC94, (2016) DEURACS reproduces the peaks arising from breakup. 24

25 Residual nucleus production 27 Al(d,x) * PHITS = INCL GEM S.Nakayama et al., RPC98,044606(2018) TENDL/PHITS are good at low/high energies. DEURACS reproduces the data in the wide energy range. 25

26 Future plan for JENDL-5 Revision of test files based on the feedback of benchmark results Evaluation of covariance Evaluation of fission product yields Additional new thermal scattering law data Calculation of recoil nucleus spectrum for estimation of KERMA factor ENDF formatting of charged particle induced reaction data Documentation Please feel free to contact us: 26