234 U( n,f ) and 232 Th( n,f )

1. 234U(n,f) and 232Th(n,f) FIC – nTOF

2. Analysis of the detector signal relative cross section calculation “Average signals” Pulse fitting Select fitted pulses “Gamma – Flash” fitting “Gamma – Flash” fitting Subtract “average signal” Add same samples Add fADC content Fit pulses Apply threshold End of run false End of run Threshold correction false true Create “average signals” true Calculate relative cross section to 235U and 238U Store results

3. Analysis of the detector signal Typical “average signals” These “averages” are fitted to the detector signal with the above function before are subtracted

4. Analysis of the detector signal Typical detectors signal pulse fitting Average signals are created for each fADC channel (magenta). From the detector signal (black) the average is subtracted (cyan). The pulses are fitted with the “pulse function” (red). “pulse function”

5. Analysis of the detector signal Correction for threshold Function used to fit the amplitude distribution Correction = (2nd Peak Integral with no threshold)/(2nd Peak Integral with threshold) Correction x YieldWithThreshold = Yieldcorrected 238U amplitude distribution of 234U run, correction = 1.2

6. Analysis of the detector signal σ(Εn) = f(σ(t), σ(d)) in the order of 10-3 σ(t) is both gamma flash and peak fitting error σ(d) is the error in the distance (0.5 mm) and in “ nTOF resolution function” ? For the calculation of relative cross section was used the “thin target approximation” formula σ(csrel) = f(σ(m), σ(Y)), both for measured and reference sample σ(m) is the sample mass error σ(Y) is the statistical error of the counts for each energy Both errors are plotted at the graphs presented The graphs have logarithmic binning and 500 bins per decade

7. 234U fission campaign FIC targets* *source : Neutron Induced Fission Cross-Section Measurements with FICs Detectors. Vladimir Konovalov

8. Fission Yield Orange no threshold Black with threshold (400)

9. Efficiency correction due to threshold Amplitude distribution without threshold fitted to correct for the lost fission events. Threshold was set to 400. Correction = 1.2 Correction = 1.18 Correction = 1.14

10. 234U relative cross section to 235U

11. 234U relative cross section to 238U

12. 238U relative cross section to 235U

13. 238U cross section (derived from 238U relative cs to 235U and ENDF)

14. 234U cross section (derived from 234U relative cs to 235U and ENDF)

15. 232Th fission campaign FIC targets* *source : Neutron Induced Fission Cross-Section Measurements with FICs Detectors. Vladimir Konovalov

16. Fission Yield Orange no threshold Black with threshold (600)

17. Efficiency correction due to threshold Amplitude distribution without threshold fitted to correct for the lost fission events. Threshold was set to 600. Correction = 1.3 Correction = 1.25 Correction = 1.26

18. 232Th relative cross section to 235U

19. 232Th relative cross section to 238U

20. 238U relative cross section to 235U

21. 238U cross section (derived from 238U relative cs to 235U and ENDF)

22. 232Th cross section (derived from 232Th relative cs to 235U and ENDF)