1. Data processing in the Activation technique experiment. Making stacked or sandwiched in the repeated order of Al-Cu-Mo. Irradiation of the samples Using HPGe-detector system, data were taken for sample foils and standard sources.

2. Calculation of Efficiency At first, we need to calculate the efficiency of the standard sources. Formula :

3. Where, Net area means the area under a photo peak. A0 ; Initial activity of the standard sources. Usually, it is written on the source. : Disintegration constant = 0.693 / T 1/2 T 1/2 : is the half-life of the source I  : intensity per decay of the gamma peak energy. t : Decay time ( Data taken date- source production date) However, the tables of measured efficiencies at different distances are given below

4. Table for efficiency measurement Name of sources Initial activity (  Ci) A 0 Half-Life (T 1/2 ) Gamma ray energy E  ( KeV) Intensity per decay (I  ) % Counting time (sec) Counts of peak area ( Net area) CPS  relative error (%) Efficiency  relative error (%) 57 Co9.938271.79 days 122.0606585.33600 12949  14021.5816  0. 233 0.0474 136.4735010.85 1713  742.855  0.12 33 0.0493 137 Cs10.4930.07 years 661.65785.1600 20749  16834.5816  0. 28 0.0110  0.0001 54 Mn10.13312.1 days 834.84199.976600 3864  746.44  0.123 3 0.0092  0.000 2 60 C09.4205.271 years 1173.22899.89600 8045  11613.4083  0. 1933 0.0051  0.000 1 1332.49099.98 6953  10811.5883  0. 18 0.0044  0.000 1

5. Measured Efficiencies at different source to detector distances

8. Measurement of Beam/ Proton flux

9. For measuring beam flux, we used the Cu samples numbered 1, 4 & 7 from group A considering incident beam beam energies at 30 MeV, 25.2 MeV & 20.2 MeV respectively. The beam energy degradation was calculated using computer program SRIM-2003.

10. Formula for Flux calculation where, CPS: Net area under a photo peak / counting time : Disintegration constant = 0.693 / T1/2 T 1/2 : is the half-life of the source I  : Gamma ray intensity

11.  : Efficiency of the detector  : Known cross section value T irr : irradiation time. t d : Decay time [( Start of counting time-end of irradiation time) +( 0.5*Counting time)] N: Total number of target nuclide = W  F  N A / Atomic weight of natural Copper W= Weight of the samples F = Isotopic abundance N A = Avogadro’s number

12. Decay data of the produced radionuclides Produced NucleiHalf-lifeDecay mode (%)Gamma ray Energy E  (keV) Intensity I  (%) Contributing reactionsThreshold Energy (MeV) 96g Tc4.28 dEC (100)778.224 812.58 849.92 1126.96 1200.2 99.76 82.0 98.0 15.2 0.37 96 Mo(p, n) 97 Mo(p,2n) 98 Mo(p,3n) 96m Tc decay -3.79 -10.69 -19.42 95m Tc61.0 d204.117 582.082 835.149 63.25 29.96 26.63 95 Mo(p, n) 96 Mo(p, 2n) 97 Mo(p, 3n) 98 Mo(p, 4n) -2.47 -11.74 -18.44 -27.09 95 Tc20.0 hEC (100)765.794 1073.713 93.82 3.74 95 Mo(p, n) 96 Mo(p, 2n) 97 Mo(p, 3n) 98 Mo(p, 4n) -2.47 -11.74 -18.44 -27.09 94 Tc293 mEC (100)702.626 849.92 871.082 99.6 95.7 100 94 Mo(p, n) 95 Mo(p, 2n) 96 Mo(p, 3n) 97 Mo(p, 4n) -5.03 -12.53 -21.56 -28.38 62 Zn9.186 h EC+  + (100) 548.35 596.7 15.2 25.7 63 Cu(p, 2n) 65 Cu(p, 4n) -13.3 -31.08 65 Zn244.26 d EC+  + (100) 1115.550.6 65 Cu(p, n)-2.17

13. Value of proton flux No of sampleFlux for gamma energy (KeV)Source to detector distance (cm) 548.38596.7 1 5.48  10 8 5.37  10 8 50 4 4.50  10 8 4.34  10 8 10 7 2.11  10 8 2.05  10 8 10

14. Calculation of Cross-section Cross-sections were calculated using the well known activation formula. Where, the symbols have their usual meanings.

15. The obtained Cross-sectional values are as follows: Produced NuclideValue of cross-sections at different incident energy 30.3 MeV26.3 MeV24.8 MeV17.9 MeV13.5 MeV8.43MeV 96g Tc184 mb167 mb158 mb 96 Nb3.73 mb3.1 mb2.6 mb 95m Tc55.4 mb50.5 mb67.5 mb50 mb40.9 mb 95 g Tc107 mb126 mb189 mb 94g Tc77.1 mb85.3 mb73.3 mb

16. Conclusions We tried to our best to report a reliable data set of the investigated radio nuclides. We do believe that we have done our job successfully.

17. Acknowledgment The author would like to give special thanks to the staffs of the Cyclotron Laboratories (KIRAM, Seoul) for their cordial help in performing the irradiations of the samples. This research received financial support from the MOST (Project Number M2-0409- 00-0001

18. References: 1.Ziegler, J.F., Biersack, J.P., Littmark, U., SRIM 2003 code, Version 96.xx. The stopping and range of ions in solids. Pergamon, New York. 2.E. Browne, R.B. Firestone, Table of Radioactive Isotopes, in: V.S. Shirley (ed.), Wiley, New York, 1986. 3.Reaction Q-values and thresholds, Los Alamos National Laboratory, T-2 Nuclear Information Service. Available from http://t2.lanl.gov/data/qtool.html 4. Monitor cross-section data Available at http://www-nds.iaea.org/medical/cup62zn.html

19. 5. Takacs, S., Tarkanyi, F., Sonck, M., Hermanne, A., 2002. Investigation of the nat Mo(p,xn) 96mg Tc nuclear reaction to monitor proton beams: new measurements and consequences on the earlier reported data. Nucl. Instrum. Method Phy. Res. B 198, 183-196. 6. Uddin, M.S., Hagiwara, M., Tarkanyi, F., Ditroi, F., Baba, M., 2004. Experimental studies on the proton-induced activation reactions of molybdenum in the energy range 22- 67 MeV. Applied Radiation and Isotopes 60 (2004) 911-920. 7. Bonardi, M., Birattari, C., Groppi, F., Sabbioni, E., 2002. Thin-target excitation functions, cross-sections and optimized thick-target yields for nat Mo(p, xn) 94g,95m,95g,96(m+g) Tc nuclear reactions induced by protons from threshold up to 44 MeV. No Carrier Added radiochemical separation and quality control. Applied Radiation and Isotopes 57 (2002) 617-635.