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

WPEC 2006 May 4-5, 2005 Present Status of JENDL Project J. Katakura 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

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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 Division of Environment and Radiation Engineering Sciences Environmental Research, which contribute to the international Creation of innovative nuclear systems by nuclear nonproliferation, advanced nuclear science and reactor engineering Radiation Research to establish reasonable radiation protection � Reactor Physics Group � Research Group for Environmental Science Thermal and Fluid Engineering Group � Research Group for Analytical � Science � � Research Group for Laser Probing � Nuclear Transmutation Technology Group � � Research Group for Applied Radiation Physics � � � Innovative Nuclear Science Research Group Radiation Effect Analysis Group � � Nuclear Data Center � SPEEDI �������������������������� Research Group for Radiation Protection � � Research Group for Utilization of Radioactive Waste Resources � � Division ofFuels and Materials Engineering Division of Nuclear Applied Heat R & D for basis of advanced nuclear fuel cycle and Technology safety & reliability of atomic power plant Development of high temperature gas cooled reactor and nuclear heat application system including � hydrogen production � Research Group for Actinides Separation Chemistry � Research Group for Aqueous Separation Process Chemistry � HTGR Cogeneration Design � � � Assessment Group � Research Group for Transuranium Fuel Behavior � IS � Process Technology Group � Corrosion Resistant Materials Development Group � HTGR � IS Coupling Technology Group � Research Group for Corrosion Damage Mechanism Glove box with high-purity � High Temperature Fuel � � Material Group � Research Group for Intense Irradiation Field Materials inert atmosphere HTTR � � � IS process � HTGR Performance & Safety Demonstration Group Hydrogen production Structural and Functional Materials Development Group Facility Research Co-ordination and Promotion Office

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)

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.

GMA analysis for 243 Cm fission 243 Cm fission 10 2 R.R.Fullwood+ ('70) Cross Section (b) Present M .G.Silbert ('76) JENDL-3.3 E.F.Fom ushkin+ ('87) Maslov et al. E.F.Fom ushkin+ ('90) E.F.Fom ushkin+ ('91) B.I.Fursov+ ('97) B.I.Fursov+ ('97) 10 1 10 0 10 2 10 3 10 4 10 5 10 6 10 7 Neutron Energy (eV)

Ratio to JENDL-3.3 243 Cm fission Cross Section Ratio (JEN DL-3.3)/GM A 1.2 standard deviation of GM A 1.0 0.8 0.6 10 2 10 3 10 4 10 5 10 6 10 7 Neutron Energy (eV)

GMA analysis for 238 Pu fission

Ratio to JENDL-3.3 238 Pu fission Cross Section Ratio 1.4 (JENDL-3.3)/GMA standard deviation of GMA results 1.2 1.0 0.8 0.6 10 3 10 4 10 5 10 6 10 7 Neutron Energy (eV)

Systematics of optical model parameters Potential Depth (MeV) 238 U 238 U 208 Pb, 209 Bi 208 Pb, 209 Bi Diffuseness (fm) 90 Zr, 93 Nb 90 Zr, 93 Nb 232 Th 232 Th 120 Sn 184 W, 197 Au 184 W, 197 Au 120 Sn 56 Fe, 58 Ni, 63 Cu 56 Fe, 58 Ni, 63 Cu Mass A Mass A

s-wave and p-wave neutron strength functions

Comparison with JENDL-3.3 Angular Distributions of Elastically Scattered Neutrons JENDL-3.3 This work d σ /d Ω (barn/sr) C.M. Angle (degree)

JENDL High Energy File 1 H, 12 C, 14 N, 16 O, 27 Al, 50,52,53,54 Cr, 54,56,57,58 Fe, 1 st priority 58,60,61,62,64 Ni, 63,65 Cu, 180,182,183,184,186 W, (39) 196,198,199,200,201,202,204 Hg, 204,206,207,208 Pb, 209 Bi, 235,238 U 9 Be, 10,11 B, 24,25,26 Mg, 28,29,30 Si, 39,41 K, 2 nd priority 40,42,43,44,46,48 Ca, 46,47,48,49,50 Ti, 51 V, 55 Mn, 59 Co, (43) 90,91,92,94,96 Zr, 93 Nb, 92,94,95,96,97,98,100 Mo, 238,239,240,241,242 Pu 2 H, 6,7 Li, 13 C, 19 F, 23 Na, 35,37 Cl, 35,38,40 Ar, 3 rd priority 64,66,67,68,70 Zn, 69,71 Ga, 70,72,73,74,76 Ge, 75 As, 89 Y, 181 Ta, (40) 197 Au, 232 Th, 233,234,236 U, 237 Np, 241,242,242m,243 Am, 243,244,245,246 Cm 4 th priority 15 N, 18 O, 74,76,77,78,80,82 Se, 113,115 In (10) Nuclides with red color (66) : Released in March 2004 as JENDL/HE-2004

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) 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 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

JENDL PKA/KERMA File - Purpose for the estimation of the radiation damage in solid materials - Incident Particle: neutron (< 50 MeV) MF quantities 3 cross sections and KERMA factor 4 angular distributions for discrete levels 6 double-differential light particles and PKA cross sections 63 DPA cross sections 66 damage energy spectra