Message: Re: Cross Section Data Base  Not Logged In (login) 
Andrea, thanks a lot for quick answer. I have used verbose level (such as /tracking/verbose 2), as you recomend , but for several beamOn, because increasing size of OUT file. During simulation i getting all statistical results and their dispertion for all running processes and their secondaries. U can see summary Out file:
Like this: Target consist of 1000 disks of G4_Pb material cylindrical shape with R(mm) = 51 Width(mm)= 0.61 Total Length(mm)= 610 Position of beam Z(mm) = 0.01 1.) Beam particle proton 2.) Beam Energy(MeV) 470 3.) Number of events 10000 4.) Average number of msc 170.775 Diviation: 43873.2 RMS: 209.459 Delta: 6.28378 5.) Average number of hIoni 7.7732 Diviation: 32.812 RMS: 5.72817 Delta: 0.171845 6.) Average number of eIoni 23.9463 Diviation: 722.34 RMS: 26.8764 Delta: 0.806292 7.) Average number of eBrem 2.4322 Diviation: 45.426 RMS: 6.73988 Delta: 0.202196 8.) Average number of annihil 0.6999 Diviation: 1.70144 RMS: 1.30439 Delta: 0.0391318 9.) Average number of phot 13.5585 Diviation: 224.376 RMS: 14.9792 Delta: 0.449375 10.) Average number of compt 9.0677 Diviation: 107.948 RMS: 10.3898 Delta: 0.311694 11.) Average number of Decay 0.0525 Diviation: 0.0613438 RMS: 0.247677 Delta: 0.0074303 12.) Average number of PhotonInelastic 0.0007 Diviation: 0.00069951 RMS: 0.0264483 Delta: 0.000793448 13.) Average number of hadElastic 10.5745 Diviation: 113.153 RMS: 10.6373 Delta: 0.31912 14.) Total inelastic (n,n) reactions! 1.0563 Diviation: 2.12393 RMS: 1.45737 Delta: 0.0437211 15.) Average number of NeutronInelastic_(n;xy) 0.1686 Diviation: 0.184374 RMS: 0.429388 Delta: 0.0128816 16.) Average number of NeutronInelastic_(n;xn) 0.481 Diviation: 0.702239 RMS: 0.837997 Delta: 0.0251399 17.) Average number of NeutronInelastic_Z 0.4765 Diviation: 0.694048 RMS: 0.833095 Delta: 0.0249929 18.) Average number of NeutronInelastic_XY 0.0045 Diviation: 0.00447975 RMS: 0.0669309 Delta: 0.00200793 19.) Average number of nCapture 0.0033 Diviation: 0.00328911 RMS: 0.0573508 Delta: 0.00172052 20.) Average number of ProtonInelastic 0.7177 Diviation: 0.341807 RMS: 0.584642 Delta: 0.0175393 21.) Average number of ProtonInelastic_Z 0.6841 Diviation: 0.342507 RMS: 0.585241 Delta: 0.0175572 22.) Average number of ProtonInelastic_XY 0.0224 Diviation: 0.0218982 RMS: 0.147981 Delta: 0.00443942 23.) Average number of CHIPSNuclearCaptureAtRest0.0044 Diviation: 0.00438064 RMS: 0.0661864 Delta: 0.00198559 24.) Average number of CHIPSNuclearCaptureAtRest_Z 0.0044 Diviation: 0.00438064 RMS: 0.0661864 Delta: 0.00198559 25.) Average number of dInelastic 0.0003 Diviation: 0.00029991 RMS: 0.0173179 Delta: 0.000519537 26.) Average number of dInelastic_Z 0.0002 Diviation: 0.00019996 RMS: 0.0141407 Delta: 0.000424222 27.) Average number of tInelastic 0.0004 Diviation: 0.00039984 RMS: 0.019996 Delta: 0.00059988 28.) Average number of tInelastic_Z 0.0004 Diviation: 0.00039984 RMS: 0.019996 Delta: 0.00059988 29.) Average number of PionPlusInelastic 0.0009 Diviation: 0.00089919 RMS: 0.0299865 Delta: 0.000899595 30.) Average number of PionPlusInelastic_Z 0.0006 Diviation: 0.00059964 RMS: 0.0244875 Delta: 0.000734626 31.) Average number of PionMinusInelastic 0.0004 Diviation: 0.00039984 RMS: 0.019996 Delta: 0.00059988 32.) Average number of PionMinusInelastic_Z 0.0004 Diviation: 0.00039984 RMS: 0.019996 Delta: 0.00059988 ##### End of outfile3(Creating by Bogdanov A.A).###### And i have detected all born neutrons and leaked too:
4.) Cumultative number of burning neutrons 7.9103 Diviation: 62.1445 RMS: 7.88318 Delta: 0.236495 5.) From (y;n) reactions 0.0007 Diviation: 0.00069951 RMS: 0.0264483 Delta: 0.000793448 6.) From inelastic (n;xn) reactions 2.0073 Diviation: 15.5348 RMS: 3.94143 Delta: 0.118243 7.) From inelastic (p;xn) reactions 5.8546 Diviation: 31.8407 RMS: 5.64275 Delta: 0.169283 8.) From inelastic (pi+;xn) reactions 0.0036 Diviation: 0.028187 RMS: 0.16789 Delta: 0.0050367 9.) From inelastic (pi;xn) reactions 0.0022 Diviation: 0.0185952 RMS: 0.136364 Delta: 0.00409092 10.) From CHIPS 0.0403 Diviation: 0.418076 RMS: 0.646588 Delta: 0.0193976 11.) From inelastic (d;xn) reactions 0.0004 Diviation: 0.00099984 RMS: 0.0316202 Delta: 0.000948607 12.) From inelastic (t;xn) reactions 0.0012 Diviation: 0.00419856 RMS: 0.0647963 Delta: 0.00194389
5.) Average number of forwardleaked neutrons 0.0018 Diviation: 0.0137968 RMS: 0.11746 Delta: 0.00352379 6.) Average number of sideleaked neutrons 6.1897 Diviation: 37.1179 RMS: 6.09245 Delta: 0.182773 7.) Average number of backwardleaked neutrons 1.066 Diviation: 4.57964 RMS: 2.14001 Delta: 0.0642003 8.) Average number of all leaked neutrons 7.2575 Diviation: 50.6848 RMS: 7.11933 Delta: 0.21358
As u can see i can get this results with including nfission process and I can compare them with results in which nfission inactivate, but in other external application for reactor physics i want to anylise Kinfinity =production/absorbation.For this calculation i have to describe Spectrum and Total Flux and Spatial distribution of external neutron source (so called target for Accelerator Driven System), but i have to prevent double checking fission processes and other, and I know that this toolkit uses ENDF multigroup library with neutron MaxE = 20MeV, that's why i have to stop simulations <20MeV with calling XS from ENDF library in Geant4. It gives definition of external source, if i'm not mistaken)
Any ideas? I'll look Physics with _HP. Sorry for long output file (i see that i copy Pb target results, but in fission materials idea of checking processes is similar ...) Best regards. Aleksey

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