[PPT] - Present Status of JENDL Project J. Katakura Nuclear Data Center PowerPoint Presentation

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Present Status of JENDL Project

J. Katakura

Nuclear Data Center Nuclear Science and Engineering Directorate Japan Atomic Energy Agency

WPEC 2006 May 4-5, 2005

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JAEA

 Japan Atomic Energy Agency

 Established on October 1, 2005  Merger of JAERI and PNC  Independent Administrative Agency

 Organization mechanism has been changed from that of JAERI

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Nuclear Science and Engineering Directorate

Director General: Mr. Osamu OYAMADA, Deputy Director General Dr. Toru OGAWA

Establish a foundation of COE for nuclear energy research and development

Division of Nuclear Data and Reactor Engineering

Reactor Physics Group
Thermal and Fluid Engineering Group
Nuclear Transmutation Technology Group
Innovative Nuclear Science Research Group
Nuclear Data Center

Division ofFuels and Materials Engineering

Research Group for Actinides Separation Chemistry
Research Group for Aqueous Separation Process Chemistry
Research Group for Transuranium Fuel Behavior
Corrosion Resistant Materials Development Group
Research Group for Corrosion Damage Mechanism
Research Group for Intense Irradiation Field Materials

Structural and Functional Materials Development Group

Division of Nuclear Applied Heat Technology

HTGR Cogeneration Design
Assessment Group
IS

Process Technology Group

HTGR

IS Coupling Technology Group

High Temperature Fuel
Material Group
HTGR Performance & Safety Demonstration Group

Division of Environment and Radiation Sciences

Research Group for Environmental Science
Research Group for Analytical

Science

Research Group for Laser Probing
Research Group for Applied Radiation Physics
Radiation Effect Analysis Group
Research Group for Radiation Protection
Research Group for Utilization of Radioactive Waste Resources

Research Co-ordination and Promotion Office

Environmental Research, which contribute to the international nuclear nonproliferation, Radiation Research to establish reasonable radiation protection Development of high temperature gas cooled reactor and nuclear heat application system including

hydrogen production

R & D for basis of advanced nuclear fuel cycle and safety & reliability of atomic power plant

Creation of innovative nuclear systems by

advanced nuclear science and reactor engineering

HTTR

IS process

Hydrogen production Facility

SPEEDI

Glove box with high-purity inert atmosphere

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Mid-term plan (Tentative Translation)

 Design precision will be enhanced by establishing nuclear data for nuclear conversion target MA and LLFP, establishing nuclear design code, and conducting reactor physics experiment.  With fuel burn-up rate becoming higher, FP and MA nuclide will be playing increasingly important

role. Thus, efforts will be made to mainly assess

such nuclear data, and to complete JENDL-4, the General-Purpose, Pre-Assessed Nuclear Data Library featuring expansive error data, so to enhance the reliability of nuclear calculation.

(From JAEA English home page)

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Recent Progress

 Evaluation of MA nuclides:

 Analyses of experimental fission cross section data with

GMA code

Th-230, 232, Pa-231, U-232, 234, 236, Np-237, Pu- 236, 238, 242, 244, Am-241, 242m, 243, Cm-242, 243, 244, 245, 246, 247, 248, Cf-249, 252 (23 nuclides)

 Evaluation of Reasonance Parameters of FP Nuclides.

 Total 212 nuclides

 89: revised, 13: newly evaluated, 69: no change, 41: no measured data.

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GMA analysis for 243Cm fission

102 103 104 105 106 107 100 101 102 Neutron Energy (eV) Cross Section (b)

R.R.Fullwood+ ('70) M .G.Silbert ('76) E.F.Fom ushkin+ ('87) E.F.Fom ushkin+ ('90) E.F.Fom ushkin+ ('91) B.I.Fursov+ ('97) B.I.Fursov+ ('97)

243Cm fission

Present JENDL-3.3 Maslov et al.

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Ratio to JENDL-3.3

102 103 104 105 106 107 0.6 0.8 1.0 1.2

(JEN DL-3.3)/GM A standard deviation of GM A

Neutron Energy (eV) Cross Section Ratio

243Cm fission

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GMA analysis for 238Pu fission

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Ratio to JENDL-3.3

103 104 105 106 107 0.6 0.8 1.0 1.2 1.4

(JENDL-3.3)/GMA standard deviation of GMA results

Neutron Energy (eV) Cross Section Ratio

238Pu fission

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Systematics of optical model parameters

232Th 238U 208Pb,209Bi 184W,197Au 120Sn 90Zr,93Nb 56Fe,58Ni,63Cu

Mass A

238U 208Pb,209Bi 232Th 184W,197Au 120Sn 90Zr,93Nb 56Fe,58Ni,63Cu

Mass A

Diffuseness (fm) Potential Depth (MeV)

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s-wave and p-wave neutron strength functions

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Comparison with JENDL-3.3

dσ/dΩ (barn/sr) Angular Distributions of Elastically Scattered Neutrons C.M. Angle (degree)

JENDL-3.3 This work

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JENDL High Energy File

2H, 6,7Li, 13C, 19F, 23Na, 35,37Cl, 35,38,40Ar, 64,66,67,68,70Zn, 69,71Ga, 70,72,73,74,76Ge, 75As, 89Y, 181Ta, 197Au, 232Th, 233,234,236U, 237Np, 241,242,242m,243Am, 243,244,245,246Cm

3rd priority (40)

15N, 18O, 74,76,77,78,80,82Se, 113,115In

4th priority (10)

9Be, 10,11B, 24,25,26Mg, 28,29,30Si, 39,41K, 40,42,43,44,46,48Ca, 46,47,48,49,50Ti, 51V, 55Mn, 59Co, 90,91,92,94,96Zr, 93Nb, 92,94,95,96,97,98,100Mo, 238,239,240,241,242Pu

2nd priority (43)

1H, 12C, 14N, 16O, 27Al, 50,52,53,54Cr, 54,56,57,58Fe, 58,60,61,62,64Ni, 63,65Cu, 180,182,183,184,186W, 196,198,199,200,201,202,204Hg, 204,206,207,208Pb, 209Bi, 235,238U

1st priority (39) Nuclides with red color (66) : Released in March 2004 as JENDL/HE-2004

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JENDL Photonuclear Data File

For Gamma-ray Induced Reaction Data up to 140 MeV Provided for applications such as electron accelerator shielding, radiation therapy and actinide-nuclide detection Photoabsorption Cross Section: Giant Dipole Resonance Model (GDR) and Quasi-deuteron Model (QDM) Additional data from KAERI File

C-13, N-15, O-17,18, Si-27, S-32,33,34,36, Cl-35,37, Ar-36,38,40, K-39,40,41, Ca-42,43,44,46,

Ti-47,48,49,50, Cr-50,53,54, Fe-57,58, Ni-61,62,64, Zn-66,67,68,70, Ge-70,72,73,74,76, Nb-94, Mo-95,97, Zr-91,92,93,94,96, Sr-84,86,87,88,90, Pd-102,104,105,106,107,108,110, Ag-107,108,109, Cd-106,108,110,111,112,113,114,116, Sn-112,114,115,116,117,118,119,120,122,124, Te-120,122,123,124,125,126,128,130, Sb-121,123, I-127,129, Cs-135,137, Pr-141, Sm-144,147,148,149,150,151,152,154, Tb-158,159, Ho-165

Stored nuclides in JENDL/PD-2004 (68 isotopes) H-2, He-3, Li-6,7, Be-9, B-10,11, C-12, N-14, O-16, F-19, Na-23, Mg-24,25,26, Al-27, Si-28,29,30, P-31,

Ca-40,48, Ti-46, V-51, Cr-52, Mn-55, Fe-54,56, Co-59, Ni-58,60, Cu-63,65, Zn-64, Zr-90, Nb-93, Mo-92,94,96,98,100, Cs-133, Gd-152,154,155,156,157,158,160, Ta-181, W-182,184,186, Au-197, Hg-196,198,199,200,201,202,204, Pb-206,207,208, Bi-209, U-235,238, Np-237

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JENDL PKA/KERMA File

Purpose

for the estimation of the radiation damage in solid materials

Incident Particle:

neutron (< 50 MeV)

cross sections and KERMA factor angular distributions for discrete levels double-differential light particles and PKA cross sections DPA cross sections damage energy spectra 3 4 6 63 66 quantities MF

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Development of Calculation Codes

 Direct process (CCOM,CCDM)

 Coupled channel optical model (ground state rotational band)  Distorted wave born approximation (vibrational collective state)

 Pre-equilibrium process (CCPM)

 2 component exiciton model

 Compound process (CCSM)

 Hauser-Feshbachspin-parity conservation, Moldauer width fluctuation correction

 Code: C++ language, Object oriented

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Capture cross section

Na-23 Mo-100 Sm-154 U-238

Cross Section (b) Cross Section (b) Cross Section (b) Cross Section (b)

CCSM JENDL-3.3 TALYS

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(n,2n)Cross section

Fe-54 Zr-90 Ta-181 Th-232

Cross Section (b) Cross Section (b) Cross Section (b) Cross Section (b) Cross Section (b)

CCSM JENDL-3.3 TALYS

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2005 Symposium on Nuclear Data

 Date: February 2th and 3th, 2006.

 November 2005 was expected before JAEA.

 Place: JAEA, Tokai.  Topics:

 Nuclear Data for Innovative Reactor Developments and Further Developments of Current Reactors,  Past and Future of Nuclear Data Research,  Status and Performance of Latest Evaluated Nuclear Data Files, and  Latest Nuclear Data Measurements.

Present Status of JENDL Project

Nuclear Data Center Nuclear Science and Engineering Directorate Japan Atomic Energy Agency

JAEA

 Japan Atomic Energy Agency

 Established on October 1, 2005  Merger of JAERI and PNC  Independent Administrative Agency

 Organization mechanism has been changed from that of JAERI

Nuclear Science and Engineering Directorate

Mid-term plan (Tentative Translation)

 Design precision will be enhanced by establishing nuclear data for nuclear conversion target MA and LLFP, establishing nuclear design code, and conducting reactor physics experiment.  With fuel burn-up rate becoming higher, FP and MA nuclide will be playing increasingly important

such nuclear data, and to complete JENDL-4, the General-Purpose, Pre-Assessed Nuclear Data Library featuring expansive error data, so to enhance the reliability of nuclear calculation.

(From JAEA English home page)

Recent Progress

 Evaluation of MA nuclides:

 Analyses of experimental fission cross section data with

Th-230, 232, Pa-231, U-232, 234, 236, Np-237, Pu- 236, 238, 242, 244, Am-241, 242m, 243, Cm-242, 243, 244, 245, 246, 247, 248, Cf-249, 252 (23 nuclides)

 Evaluation of Reasonance Parameters of FP Nuclides.

 Total 212 nuclides

 89: revised, 13: newly evaluated, 69: no change, 41: no measured data.

GMA analysis for 243Cm fission

102 103 104 105 106 107 100 101 102 Neutron Energy (eV) Cross Section (b)

Ratio to JENDL-3.3

102 103 104 105 106 107 0.6 0.8 1.0 1.2

Neutron Energy (eV) Cross Section Ratio

GMA analysis for 238Pu fission

Ratio to JENDL-3.3

103 104 105 106 107 0.6 0.8 1.0 1.2 1.4

Neutron Energy (eV) Cross Section Ratio

Systematics of optical model parameters

s-wave and p-wave neutron strength functions

Comparison with JENDL-3.3

dσ/dΩ (barn/sr) Angular Distributions of Elastically Scattered Neutrons C.M. Angle (degree)

JENDL High Energy File

JENDL Photonuclear Data File

JENDL PKA/KERMA File

for the estimation of the radiation damage in solid materials

neutron (< 50 MeV)

cross sections and KERMA factor angular distributions for discrete levels double-differential light particles and PKA cross sections DPA cross sections damage energy spectra 3 4 6 63 66 quantities MF

Development of Calculation Codes

 Direct process (CCOM,CCDM)

 Coupled channel optical model (ground state rotational band)  Distorted wave born approximation (vibrational collective state)

 Pre-equilibrium process (CCPM)

 2 component exiciton model

 Compound process (CCSM)

 Hauser-Feshbachspin-parity conservation, Moldauer width fluctuation correction

 Code: C++ language, Object oriented

Capture cross section

(n,2n)Cross section

2005 Symposium on Nuclear Data

 Date: February 2th and 3th, 2006.

 November 2005 was expected before JAEA.

 Place: JAEA, Tokai.  Topics:

 Nuclear Data for Innovative Reactor Developments and Further Developments of Current Reactors,  Past and Future of Nuclear Data Research,  Status and Performance of Latest Evaluated Nuclear Data Files, and  Latest Nuclear Data Measurements.

 Attendee: Total 91.