Evaluation of actinide nuclear data
Evaluation of actinide nuclear dataOsamu IwamotoJapan Atomic Energy Agency2010 Symposium on Nuclear Data
Applications of nuclear data
nucleosynthesisJRR-3J-PARCADSsoft error
()medical applicationnuclear dataAcceleratorReactorcrab nebulaTc-99m2recent actinide data in JENDLReleaseNo. of actinidesCovarianceJENDL-3.21994560 +6 (JENDL-3.2 Cov. File, Major)JENDL-3.32002626 + 7 (after release of JENDL-3.3, MA)JENDL/AC-20082008790JENDL-4.020107979 (all actinides, all cross sections)3Neutron induced reactions
U-235U-236U-235U-235Pa-235Nucleus(A~90)Nucleus(A~140)FissionSpallationCaptureElastic scatteringInelastic scattering4
neutron induced reaction cross sections5resolved resonanceunresolved resonancethermal235U5
Nuclear data evaluation6EXFORKALMAN, GMACRECTJNJOYCCONE6Physical quantities of actinide data in JENDL-4MFPhysical quantitiesreaction1number of neutrons per fission, Components of energy release due to fissionfission2Resonance parametersResolved RP, unresolved RP3Neutron cross sections(n,n), (n,n), (n,f),(n,g), (n,2n) ...4Angular distributions of secondary neutrons(n,n), fission5Energy Distributions of Secondary Neutrons fission 6Energy-angle distributions(n,n), (n,2n), (n,3n), (n,g)12Photon Production MultiplicitiesFission14Photon Angular DistributionsFission15Continuous Photon Energy SpectraFission31Covariances of average number of neutrons per fissionFission32Covariances of resonance parametersResolved RP33Covariances of neutron cross sections(n,n), (n,n), (n,f),(n,g), (n,2n) ...34Covariances for Angular Distributions(n,n)35Covariances for Energy DistributionsFission neutron7MF=1number of neutrons per fissionPrompt neutron (np )Delayed neutron (nd )Components of energy release due to fission
8
Prompt neutronExperimental dataSystematicsHowerton Nucl. Sci. Eng. 62, 348 (1997)Ohsawa J. Nucl. Radiochem. Sci. Eng. 9, 19 (2008)
Ohsawa(2008)9np for U isotopesNuclidesJENDL-3.3JENDL-4U-2322.453.12U-2332.482.48U-2342.35= JENDL-3.3U-2352.422.42U-2362.36= JENDL-3.3U-2372.42= JENDL-3.3U-2382.442.28
np for thermal neutron10
Experimental dataSystematicsR.J.TuttleINDC(NDS)-107/G+Special, p.29 (1979)G.Benedetti et al.Nucl. Sci. Eng., 80, 379 (1982)R.Waldo et al.Phys. Rev., C23, 1113 (1981)
-(Ac-3Z)Ac/Z
Waldo (1981)Tuttle (1979)16.698-1.144Zc+0.377AcDelayed neutron11MF=2Resolved resonanceSAMMY code (N. Larson, ORNL/TM-9179/R8, ENDF-364/R2, 2008)Unresolved resonanceASREP code (Y. Kikuchi et al., JAERI-Data/Code 99-025)12Resonance TheoryUseful in the low energy regionBreit-Wigner formulaG. Breit and E.P. Wigner Phys. Rev., 49, 519 (1936).
Resonance parameters E, n, x should be evaluated for each J and L.Reich-Moore formulaC.W. Reich and M.S. Moore Phys. Rev., 111, 929 (1958)
13 Resonance Cross Sections
235U(n,f)14 Compilation of Resonance ParametersS.F. MughabghabAtlas of neutron resonances: resonance parameters and thermal cross sections Z=1-100, Elsevier (2006)
E , n , , f for each L and JThermal cross sections Resonance integrals
Scattering radiusNeutron separation energy
15Np-237 capture cross section for thermal neutron
16Am-241 thermal capture cross section
( ) sg.s. = 620 25 IR=0.896 assumed 17total cross section18thermal capture cross section(b)Kalebin (1976)624 20Shinohara+ (1997)854 58Fioni+ (2001)696 48Bringer+ (2006)714 23Present697.1JENDL-3.3639.5
241Am thermal neutron capturesg = 620 25 S. Nakamura+ (2007) sg+m= 692 28 (IR=0.896) U fission cross sections at RRR
19Cm-243, 244(n,f)
Low resolution measurement using lead slowing-down spectrometer2020Unresolved resonance
distribution (Porter-Thomas)Width-fluctuation correction factor
:Breit-Wigner formulaAverage cross sectionASREP: Y. Kikuchi et al., JAERI-Data/Code 99-02521Result of fitting with ASREP
R =D =Gg =Gf =22MF=3, 4, 5, 6Least-squares fitting to experimental dataFission cross section (Simultaneous evaluation on KALMAN)Major actinide (U-233, 235, 238, Pu-239, 241, 242)GMAMATheoretical model calculationAll reaction cross sections, angular distribution, secondary particle spectrum model parameter adjustmentCCONESOK23
total(n,n)(n,g)(n,f)(n,2n)(n,3n)elasticMF=3Neutron induced reaction on U-23824MF=4U-238(n,n) angular distribution25
neutron spectrum
En=5.5 MeVJENDL-3.3CCONE
En=550 keVqdeg.JENDL-3.3CCONEdW/dq (b/sr)qdeg.En(MeV)25
MF=5, 6QCM(deg)ds/dW (b/sr)Direct process901800QCM(deg)ds/dW (b/sr)Pre-equilibrium process901800Compound processQCM(deg)ds/dW (b/sr)901800
U-239neutron26Simultaneous evaluation of fission cross sectionLeast-squares fittingSOK code (Kawano)First order splineExperimental data
ReactionsetsReactionsets233U13233U/235U9235U17238U/233U1238U9238U/235U18239Pu16239Pu/235U14240Pu4240Pu/235U12241Pu6240Pu/239Pu1241Pu/235U4SOK27SOK28
evaluated data1st order splinecross section ratiolinearizeexperimental data
posterior covarianceprior cov.experimental data cov.
posterior
design matrixSOK
1st order spline
Correlation matrixSOK29235 fission cross section (SOK)30
SOKU-233(n,f)/U-235(n,f) (SOK)
SOK31Time evolution of nucleon induced reaction
32incident nucleon1p state2p-1h state3p-2h statecompound statedirect processpre-equilibrium processCCONE32Reaction models in CCONE codeDirect prosessOptical modelCoupled-channel methodDistorted wave Born approximationPre-equilibrium processExciton model (2 components)Compound processHauser-Feshbach
33CCONEIncident channel
34incident nucleon1p state2p-1h state3p-2h statecompound statedirect processpre-equilibrium processCCONE34Optical model
Total cross sectionShape elastic scattering cross sectionTransmission coefficient (used in statistical model)
Optical model potential (OMP)scattering matrix(strength of scattering wavesSchrdinger equation35CCONEincident nucleon35OMP and wave function
Wave functionPotentialFe-56 + n (En=10 MeV) OMP=koning-nImaginaryreal36CCONECross section variation with OMPs
totalshape elasticreaction37CCONEDirect process
38incident nucleon1p state2p-1h state3p-2h statecompound statedirect processpre-equilibrium processCCONE38Coupled-channels optical model
U-238deformation on ground stateincident wavescattered waveground state rotational bandstrong couplings between levels39CCONECoupled-channel optical modelrotational bandDeformed nucleus
40Nuclear radiusNuclear wave functionCoupled-channels equationIntrinsic wave functionRotational wave functionCCONE
deformed OMPneutron radial wave function40
Neutron Strength Function @10 keVExp.Spherical OM calc.RRM-CC calc.s-wave (l=0)s-wave neutron strength functionglobal CC OMPS. Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007)actinideCCONE4141U-238 scattering cross section (0++2++4++6+)
CCONE42pre-equilibrium process
43incident nucleon1p state2p-1h state3p-2h statecompound statedirect processpre-equilibrium processCCONE43
pp,hp,pn,hn1,0,0,02,1,0,01,0,1,13,2,0,02,1,1,11,0,2,2p,n,g emissionPre-equilibrium processExciton model (2 components)44particleholep: protonn: neutronCCONE44Parameters in exciton modelpp,hp,pn,hn1,0,0,02,1,0,01,0,1,13,2,0,02,1,1,11,0,2,2p,n emission
transition rateemission rate of particle p-h creation by protonp-h creation by neutron45inverse reaction cross section (OM calculation)CCONEExciton model parameters
transition matrix elementstate density
CCsingle particle state densityKoning et al., Nucl. Phys. A744, 15 (2004)46CCONE1/gEfPauli correction
Dependences of spectrum and cross sections on exciton model parameters
Neutron spectrum @ En=14 MeV 47CCONEcompound process
48incident nucleon1p state2p-1h state3p-2h statecompound statedirect processpre-equilibrium processCCONE48
Decay chain on statistical model TargetdiscreteContinuum49CCONEEx49
Hauser-FeshbachWidth fluctuation correction
Normalization coefficientTransmission coefficient(OM calculation
Level density of daughter nucleusExcitation energy of targetEnergy conservationParity conservationTotal spin, parity50CCONE50Cumulative number of levels for U isotopes
Level density
discrete levelcontinuum level51CCONELevel density (Fermi gas model)
average resonance spacingspinexcitation energy dependenceparity52CCONE52Level density
Saddle point
inner-deformationouter mass asymmetryCollective enhancement (rotational level)Shell structure washoutGround stateFermi gasconstanttemperature53CCONE
g-ray strength function54
Standard LorentzianEnhanced Generalized LorentzianKopecky et al. PRC47,312 (1993), PRC41,1941(1990)
g-ray transmission coefficientCCONE54
Giant dipole resonance parameter55
SystematicsCCONEFission
Transition statePenetrability of a parabolic barrier double barriersTransmission coefficient56barrier curvaturebarrier heighttransition state energyCCONE56Fission cross sections for U isotopes
CCONE57U capture cross section
CCONE58U-238(n,2n)
Frehaut data without correctionCCONE59
Capture cross sections for Pu and N60
Pu-237Pu-239Pu-241Pu-244Pu-246Np-235Np-236Np-237Np-239Np-238JENDL-3.3JENDL-4.0CCONENp fission cross sections
GMACCONECCONE61CCONENeutron spectrum
CCONE62WPEC Subgroup 29 U-235 Capture Cross Section in the keV to MeV Energy Region63
Problem of integral experiment sodium voided reactivity in BFSMOXSensitivity to 235U capture cross sectionsodium voided reactivity
6464
Possible overestimation of capture cross section of U-235U-235 capture cross sectioncapture cross section/ fission cross sectio
