Status and future plan of JENDL Osamu Iwamoto Nuclear Data Center - PowerPoint PPT Presentation

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

In Introduction JENDL-4.0 was released in 2010 with improving fission- product, 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

JENDL Photonuclear Data F Fil ile 2016 JENDL/PD-2016 • Released in Dec. 2017 • 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 beta- stability line (based on experimental data) • Expanded version: 2681 nuclides covering a wide range of unstable ones (mainly model calculations) 3

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

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

JENDL Activation Cross Section File f 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 293.6 K 6

New evalu luation for C-13 13 Neutron capture cross section 7

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

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

Topics of JENDL-5 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

ion JENDL-5 a 1 The first test v versio • JENDL-5 a 1 was created in 2018 • Updated and newly evaluated elements in JENDL- 5 a 1 • 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

JENDL-5 Lig ight nucleus evalu luatio ion • 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

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

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

JENDL-5 Structural materia ial Isomer productions are important as reactor dosimeter and neutron flux monitor. CCONE calculations simultaneously reproduce isomer and total cross sections. 93 Nb (n,n') 93 Nb (n,2n) 2.5 JENDL–4.0 JEFF–3.3 (m.s.) ENDF/B–VIII.0 JENDL–5a1 (m.s.) 94 Lashuk+ 1.5 JEFF–3.3 92 Simakov+ JENDL–5a1 77 Kozur+ 2 74 Birjukov+ 73 Vanheerden+ Cross Section (b) Cross Section (b) 84 Lychagin+ 70 Goebel+ 63 Thomson 80 Frehaut+ 1.5 1 96 Ikeda+ (m.s.) 63 Glazkov 80 Prokopets 93 Wagner+ (m.s.) JENDL–4.0 77 Veeser+ 88 Wagner+ (m.s.) ENDF/B–VIII.0 77 Kozur+ 88 Gayther+ (m.s.) JEFF–3.3 76 Holub+ 1 81 Ryves+ (m.s.) JENDL–5a1 72 Mather+ 80 Taylor+ (m.s.) 0.5 ENDF/B–VIII.0 (m.s.) JEFF–3.3 (m.s.) 0.5 JENDL–5a1 (m.s.) 11 Honusek+ (m.s.) 93 Ikeda+ (m.s.) 07 Mannhart+ (m.s.) 91 Molla+ (m.s.) 00 Kiraly+ (m.s.) 91 Smith+ (m.s.) 00 Fessler+ (m.s.) 90 Santry+ (m.s.) 99 Filatenkov+ (m.s.) 90 Kimura+ (m.s.) 0 0 0 5 10 15 20 10 15 20 Incident Neutron Energy (MeV) Incident Neutron Energy (MeV) A. Ichihara, JNST 53,2049 (2016) 15

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

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

Preliminary ry evalu luation of Bi-209 209 18

JENDL-5 actin inide evalu luation • 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

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

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

Thermal scattering data for light water Y. Abe et al., NIMA 735 (2014) 568-573 (MD based approach) Total cross section 91 Zaitsev et al. (297 K) 91 Zaitsev et al. (303 K) Cross Section (b/molecule) 66 Russell et al. 61 Heinloth 10 3 JENDL–4.0 (296 K) ENDF/B–VIII.0 (293.6 K) JEFF–3.3 (293.6 K) JENDL–5a (300K ) 10 2 10 1 10 –5 10 –4 10 –3 10 –2 10 –1 10 0 Incident Neutron Energy (eV) 22 *JENDL-4.0, ENDF/B-VIII.0, JEFF-3.3 includes the contribution from H only.

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

Neutron emission 12 C( d,xn )@102MeV (DDXs) 12 C( d,xn )@18MeV (TTYs) 3.5 o (x1) 0 o (x1) 9 o (x10 -2 ) 15 o (x10 -2 ) S. Nakayama et al., RPC94, 014618 (2016) DEURACS reproduces the peaks arising from breakup. 24

Residual nucleus production 107 Pd( d,x )Rh@200MeV 27 Al( d,x ) 22 Na@20-100MeV S.Nakayama et al., RPC98,044606(2018) * PHITS = INCL-4.6 + GEM TENDL/PHITS are good at low/high energies. → DEURACS reproduces the data in the wide energy range. 25

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: jendl@jaea.go.jp 26