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

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

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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

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Status and future plan

  • f JENDL

Osamu Iwamoto Nuclear Data Center Japan Atomic Energy Agency

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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

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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)

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Nuclides in JENDL/PD

4 (Standard) (Extended) 68 nuclides

Neutron number Proton number

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Evalu luated data for O-16( 16(g,n ,n)O )O-15 15

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Photon energy (MeV) Cross section (mb)

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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

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New evalu luation for C-13 13

Neutron capture cross section

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Eu evaluation with measurement

  • f J-PARC ANNRI

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151Eu(n,g)152Eu

Cross section (kb)

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Simple estimation of activitiy of concrete ir irradiated by BWR neutron spectrum

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Activity/clearance level (a.u.) Time after irradiation (year)

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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?)

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The first test v versio ion 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.

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JENDL-5 Lig ight nucleus evalu luatio ion

  • New R-matrix code AMUR
  • Preliminary evaluation of N-15, O-16, F-19
  • Covariance

12 JENDL-4.0(=JENDL-3.3) covariance evaluation

K.Shibata et al. JNST44.1(2007)

GMA evaluation Uncertainty

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Result of resonance analysis

Uncertainty

  • f 15N(n,tot) cross-sections

sth : ATLAS-2006 (n,n1) thr.

15N(n,tot), exp : Zeitnitz+ (1997)

AMUR fit Cov.

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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

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JENDL-5 Structural materia ial

15 Isomer productions are important as reactor dosimeter and neutron flux monitor. CCONE calculations simultaneously reproduce isomer and total cross sections.

  • A. Ichihara, JNST 53,2049 (2016)

5 10 15 20 0.5 1 1.5 2 2.5

93Nb (n,n')

Incident Neutron Energy (MeV) Cross Section (b)

JENDL–4.0 ENDF/B–VIII.0 JEFF–3.3 92 Simakov+ 94 Lashuk+ 77 Kozur+ 74 Birjukov+ 73 Vanheerden+ 63 Glazkov 63 Thomson 70 Goebel+ 93 Wagner+ (m.s.) 96 Ikeda+ (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.) JENDL–5a1

10 15 20 0.5 1 1.5

93Nb (n,2n)

Incident Neutron Energy (MeV) Cross Section (b)

JENDL–4.0 ENDF/B–VIII.0 80 Frehaut+ 84 Lychagin+ 80 Prokopets 77 Veeser+ 77 Kozur+ 72 Mather+ 76 Holub+

99 Filatenkov+ (m.s.) 00 Fessler+ (m.s.) 93 Ikeda+ (m.s.) 91 Molla+ (m.s.) 91 Smith+ (m.s.) 90 Santry+ (m.s.)

JEFF–3.3 (m.s.)

00 Kiraly+ (m.s.) 11 Honusek+ (m.s.) 07 Mannhart+ (m.s.) 90 Kimura+ (m.s.)

JENDL–5a1 (m.s.) JEFF–3.3 JENDL–5a1

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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)

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Evaluated results for Te Te and I I isotopes

natTe(n,n0)

Te elastic scattering 17

  • K. Shibata, JNST 52, 490 (2015)
  • K. Shibata, JNST 52, 1174 (2015)
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Preliminary ry evalu luation of Bi-209 209

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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.

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Am Am-241 resonance analysis with new measurement by ANNRI

20 Transmission Capture yield

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Energy dependence of dela layed neutron

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Summation calculation by energy dependent systematics of fission product yields

  • F. Minato, JNST 55, 1054 (2019)
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Thermal scattering data for light water

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  • Y. Abe et al., NIMA 735 (2014) 568-573

JENDL–4.0 (296 K) ENDF/B–VIII.0 (293.6 K) JENDL–5a (300K ) JEFF–3.3 (293.6 K) 66 Russell et al. 91 Zaitsev et al. (297 K) 61 Heinloth

Incident Neutron Energy (eV) Cross Section (b/molecule)

91 Zaitsev et al. (303 K)

10–5 10–4 10–3 10–2 10–1 100 101 102 103

*JENDL-4.0, ENDF/B-VIII.0, JEFF-3.3 includes the contribution from H only.

(MD based approach)

Total cross section

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Deuteron induced reaction: DEURACS

Elastic scattering Elastic breakup Absorption Inelastic breakup Inelastic breakup ：CCONE ：DEURACS n + A d + A p + A

: n : p

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Neutron emission

12C(d,xn)@102MeV (DDXs)

0o (x1) 15o (x10-2)

12C(d,xn)@18MeV (TTYs)

3.5o (x1) 9o (x10-2)

DEURACS reproduces the peaks arising from breakup. 24

  • S. Nakayama et al., RPC94, 014618 (2016)
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Residual nucleus production

27Al(d,x)22Na@20-100MeV 107Pd(d,x)Rh@200MeV

* PHITS = INCL-4.6 + GEM

TENDL/PHITS are good at low/high energies. → DEURACS reproduces the data in the wide energy range.

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S.Nakayama et al., RPC98,044606(2018)

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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

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Please feel free to contact us:

jendl@jaea.go.jp