Current and future development of JENDL

Osamu Iwamoto

Japan Atomic Energy Agency

History of JENDLVersion JENDL-1 JENDL-2 JENDL-3.1 JENDL-3.2 JENDL-3.3 JENDL-4.0

Purpose FR LWR, FR General General General General

Release 1977 1982 1990 1994 2002 2010

Max

energy

15 MeV 20 MeV 20 MeV 20 MeV 20 MeV 20 MeV

Nucleiisotopes + elements

66 + 6 173 + 8 305 + 19 318 + 22 335 + 2 405 + 1

g-ray

prod.

0 0 59 66 114 354

DDX 0 0 0 0 60 318

Cov. 0 0 1 1 20 95

The latest version JENDL-4.0 aimed at contributing to R&D on innovative reactor, high burn-up reactor, use of MOX fuel. Data for FP and MA were intensively revised and covariance data for actinides were enhanced.

Organization & stakeholders related to JENDL

Institutes

Universities

Companies

Regulation Authority

Atomic Energy Society of Japan

Sigma Advisory Committee

Nuclear Data Committee

Symposium on Nuclear Data

Annual Meeting, Fall Meeting

(roadmap, request list, …)

JENDL

Japan Atomic Energy Agency

Nuclear Data Center

Nuclear Sci. and Eng. Center

Nuclear Data and Reactor Eng. Div.

RG for Reactor Phys. and Std. Nuclear Code System

JENDL Committee

information exchange

advice, cooperation

Stakeholders(evaluation)

(validation)

Atomic Energy Society of Japan2018 Fall MeetingND & accelerator committee planned a joint session:

• Compact Accelerator Neutron Source and Nuclear Data Needs

• New neutron spectrum formulation of Be+p reaction for design and applications of compact neutron sources, Y. Wakabayashi (RIKEN)

• Needs for neutron source and nuclear data in developments of an active neutron non-destructive system, Y. Toh (JAEA)

• Industrial applications (mainly medical) of small accelerators and nuclear data for those applications, T. Tadokoro (Hitachi, Ltd.)

2018 Symposium on Nuclear data

Presentatons related to ND needs

• Current Status and Future Perspectives of Reactor Physics • Needs and application of covariance data, G. Chiba (Hokkaido Univ.)

• Nuclear Data Applications• Requests from characterization for decommissioning to nuclear

data, K. Tanaka (IAE)• Nuclear data required for measurements of reactivity and nuclear

material composition, Y. Nauchi (CRIEPI)• Development of Active Neutron NDA System, Y. Toh (JAEA)

• Data Needs from New Fields• Nuclear data and its preparedness for nuclear non-proliferation and

security, H. Sagara (Tokyo Tech)• Geological Disposal of High-Level Radioactive Waste: Long-term

Safety and Reduction of Environmental Impact, H. Asano (RWMC)

6

JENDL CommitteeJapan Atomic Energy Agency

Chair K. Nakajima, Kyoto University

Subcommittee on Nuclear Data (H. Harada, JAEA)

ENSDF Group (H.Iimura, JAEA)

Japanese Nuclear Data Measurement Network (K. Nishio, JAEA)

Activation Cross Section Evaluation WG (N. Iwamoto, JAEA)

Covariance Data Use Promotion WG (G. Chiba, Hokkaido Univ.)

Subcommittee on Reactor Constants (K. Okumura, JAEA)

Reactor Integral Test WG (K. Yokoyama, JAEA)

Shielding Integral Test WG (C. Konno, JAEA)

WG on Evaluation of Nuclide Generation and Decay Heat

(F. Minato, JAEA)

Nuclear Data Processing Program WG (M. Tokashiki, NFI)

Subcommittee on International Strategy (T. Fukahori, JAEA)

International Strategy WG (A. Kimura, JAEA)

Advisory Subcommittee on Development of JENDL • Established under JENDL Committee on FY 2013 to

discuss the subject concerning on development of next JENDL

• Members of the subcommittee were selected from developers and users of JENDL and researchers on nuclear data measurements in universities, companies and national institutes.

• Discussed guidelines on next JENDL with exchanging ideas on problems of JENDL and its solution from each view point

Final report:Guideline for Developing Next JENDLJAEA-Review 2014-046 (in Japanese)

Recommendation:

• Need to emphasize backends such as reactor decommissioning and radioactive waste disposal

• Extend variety of data for various application fields of radiation other than nuclear fission reactor

• Integrate special purpose libraries and improve completeness to improve convenience

8

Recent and future release of JENDL We are trying to develop nuclear data libraries to meet needs in the new era.

9

Special Purpose FileRecently released:

JENDL/AD-2017: activation CS file for decommissioningJENDL/PD-2016: new photonuclear reaction data file

To be released:JENDL/ImPACT-2018: LLFP transmutation CS

General Purpose FileJENDL-5: developing next version of JENDL

JENDL/AD-2017 Activation Cross Section File for Nuclear Decommissioning

• For evaluation of radioactive inventoryon decommissioning of nuclear facilities

• Neutron-induced nuclear reactions (except for Fe-56 for proton incident one)

• Includes 311 nuclides (which lead to production of 221 RI)

• Energy range: up to 20 MeV

• Pointwise CS data at 0 K and 293.6 K

10

Result of C-13(n,g)C-14

11

Neutron capture cross section

Direct capture contribution

Eu evaluation with measured data by ANNRI at J-PARC

12

151Eu(n,g)152EuC

ross

sec

tio

n (

kb)

AD-2017

Analyzed with REFIT code

JENDL/ImPACT-2018JENDL LLFP transmutation cross section File 2018

• R&D program for Reduction and Resource Recycling of High-level Radioactive Wastes through Nuclear Transmutation

• Aiming at establishing reasonable nuclear transmutation methods which will enable these wastes to be converted into stable nuclides or short-lived ones

• JENDL/ImPACT-2018 contains 163 nuclides which could produced in transmutation of LLFPs (Se-79, Zr-93, Pd-107, Cs-135).

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This work was funded by the ImPACT Program of the Council for Science, Technology and Innovation (Cabinet Office, Government of Japan).

14

JENDL/ImPACT-2018

20 MeV

200 MeV

JENDL-4.0 (partly revised)

New data New data

10-5 eV

1 MeV

200 MeV

Cross-sections :・ Elastic scattering, (n,g), etc・ Isotope production・ Double-differential cross-sectionsFormat :・ENDF-6 format

neutron proton

contains 163 nuclides which could produced in transmutation of LLFPs (Se-79, Zr-93, Pd-107, Cs-135).

JENDL-5

• Improvement of accuracy and convenience for activation inventory and dose estimation

• Improve activation cross sections• Improve data needed for neutron transport calculation• Revise decay data and fission product yields• Integrate activation cross section to general purpose file

• Reduction of amount and radiotoxicity of radioactive wastes• Minor actinide data• LLFP data

• Uncertainty estimation of nuclear system• Enhancement of covariance data

• Needs from nonenergy application• All stable nuclei for neutron induced data• Charged particle induced cross sections

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Intended to contribute especially on nuclear backend and to expand data to meet needs of various applications

JENDL-5a1

• The first test version was created in 2018

• Updated and newly evaluated elements in JENDL-5alpha1

• Ga, Zr, Nb, Tc, Ru, Sb, Te, I, Pr, Gd, Er, Ta, Re, Pt, Hg, Tl, U, Pu, Am

• New evaluation of thermal scattering law for light water

16

Result of N-15 evaluation by AMUR

(n,n1) thr.

15N(n,tot)

Covariance of 15N(n,tot)

17

15N(n,n)

Cross sections for Nb-93

18

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)

0 5 10 15 200

0.5

1

1.5

2

2.5

93Nb (n,n')

Incident Neutron Energy (MeV)

Cro

ss S

ection (

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 15 200

0.5

1

1.5

93Nb (n,2n)

Incident Neutron Energy (MeV)

Cro

ss S

ection (

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

Isomer prod.

Total

Isomer prod.

Total

Evaluation of Bi-209

19

Am-241 resonance analysis with new data measured by ANNRI

20

Tran

smis

sio

nC

aptu

re y

ield

JENDL-5a

JENDL-5a

Thermal scattering law data

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

Thermal scattering cross sections for water

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)

Cro

ss S

ection (

b/m

ole

cule

)91 Zaitsev et al. (303 K)

10–5

10–4

10–3

10–2

10–1

10010

1

102

103

*JENDL-4.0, ENDF/B-VIII.0, JEFF-3.3 includes contribution only from H of H20.

(MD based approach)

Total cross section for light water

Evaluation of deuteron data

DEURACS explicitly considers the “breakup” processes.

Residual nucleus

Three production paths exist.

DEURACS was developed for deuteron data evaluation.

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CDCC

Glauber model

Glauber model

Neutron emission from d+C-1212C(d,xn)@102MeV (DDXs)

0o (x1)

15o (x10-2)

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

3.5o (x1)

9o (x10-2)

DEURACS reproduces well the peaks arising from breakup.

d-breakup

Future plan of JENDL-5• Revision of data using feedback of benchmark

results

• Covariance evaluation

• Fission product yields (Tokyo Tech.)

• Decay data

• Evaluation of thermal scattering law data

• Calculation of recoil nucleus spectrum for estimation of KERMA factor

• Integration of special purpose files such as activation c. s. file, high energy file, …

• Documentation

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Summary• Japanese nuclear data committees are shown

focusing on JENDL development.

• Nuclear data needs from various application in Japan are obtained through meetings and committees organized in AESJ and JAEA.

• Development of JENDL is now focusing on backend of nuclear energy and also intended to expand data for various applications.

• Special purpose files have been released to meet needs on time.

• JENDL-5 is under development to meets needs in Japanese stakeholders.