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 /* NRDF D1894 Data No.12                                             */
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 /* Bibliography                                                      */
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 \\BIB,12;
 D#=D1894;
 TITLE=/ Experimental studies on the proton-induced activation
         reactions of molybdenum in the energy range 22-67 MeV /;
 PURPOSE=/ To give reliable excitation functions for Mo+p reactions
           in the energy range 22-67 MeV /;
 ATH=(M.S.UDDIN'1', M.HAGIWARA'1', F.TARKANYI'2', F.DITROI'2',
      M.BABA'1');
 INST-ATH=(2JPNTOH'1', 3HUNDEB'2');
      /* '1' Cyclotron and Radioisotope Center */
 REF=ARI;
 VLP=60(2004)911;
 /* Secondary references 
    - Takacs, Private communication(2004)
    - Hagiwara, Private communication(2004)
    - JAERI-C, 2004-005(2004)138 (M.S.Uddin et al., Proc. of the 2003
      Symposium on Nuclear Data)
 RCTS=(27AL(P,X)24NA, 27AL(P,X)22NA, CU(P,X)65ZN, CU(P,X)62ZN,
       CU(P,X)56CO, 100MO(P,X)99MO, MO(P,X)93MO, MO(P,X)96TC,
       MO(P,X)94TC, MO(P,X)95TC, MO(P,X)90NB, MO(P,X)92NB, MO(P,X)96NB,
       MO(P,X)95NB, MO(P,X)86ZR, MO(P,X)88ZR, MO(P,X)89ZR, MO(P,X)86Y,
       MO(P,X)87Y, MO(P,X)88Y);
 PHQS=XSECTN;
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 /* Experimental Conditions                                           */
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 \\EXP,12;
 /* 2004-05-12 : Compiled, C.Kurokawa + N.Otuka */
 /* 2007-03-30 : Altered, Bk (ATOMKI) + N.Otuka. Reference added */
 PHQ=XSECTN;
 ENR=NAT;
 CHM=ELM;
 PHYS-FORM=SLD;
 THK-TGT=XMG/CM**2'3';
 /* '3' 49.58 micro-meter (Mo), 104.2 micro-meter (Cu) and 102
        micro-meter (Al) */
 POL-TGT=0%;
 ALGN-TGT=0%;
 ACC=CYC'4';
 /* '4' Isochronous cyclotron, k=90 MeV AVF Cyclotron */
 INST-ACC=2JPNTOH'5';
 /* '5' Cyclotron and Radioisotope Center */
 BEAM-INTNSTY=[25NA;
 POL-PRJ=0%;
 COINC=NO;
 ANT-COINC=NO;
 DET-SYS=HPGE'6';
 /* '6' To measure activities of radioactive products of the target
        and monitors. The efficiency versus energy curve of the
        detector was determined experimentally using standard gamma-ray
        point sources with known strength, 152Eu, 133Ba, 241Am. 60Co
        and 137Cs. Efficiency is also calculated using the EGS4 Monte
        Carlo Code [Nelson et al, 1985]. */
 /* Experimental Method:
    - Stacked target irradiation (Stack was assembled from
      molybdenum, copper and aluminium as Cu-Al-Mo and 10 groups were
      set together in an aluminium holder for irradiation.)
    - Energy degradation by foils (Energy degradation along the stack
      was determined using the computer program SRIM-2002 [J.F. Ziegler
      et al., The stopping and range of ions in solids, Pergamon, New
      York, 1984.] assuming the incident energy was 70 MeV.)
 /* Analysis:
    - Decay curve analysis (Two or more radionuclides emitted
      gamma-rays having very close energies, which were difficult to
      separate by the graphical analysis of the multicomponent decay
      curve, were analyzed using the difference in half-life of the
      nuclides by plotting the photon emission rate as a function of
      time.)
 /* Gamma energies given (except 90Tc and 90Nb) are obtained by private
    communication with authors. */
 /* Related references 
    - V.N.Levkovskij, LEVKOVSKIJ, (1991).
    (No comments for the comparison with present data). See also EXFOR
    A0510.
 RCT=MO(P,X)90NB;
 DET-PARTCL=GAMMA'38';
 /* '38' Delayed gamma from 90Nb (ground state) */
 ANL=INCASC'39';
 /* '39' Particle and Heavy Ion Transport code System (PHITS) [H.
         Iwase et al., J. Nucl. Sci. Technol. 39(2002)1142]. */
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 /* Descriptive Parameters                                            */
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 \\DATA,12;
 SYS-ERR=(5.8%'7',[3%'8');
 /* '7' Uncertainty in monitor flux */
 /* '8' Uncertainty in efficiency calibration of gamma ray */
 STATIST-ERR=5%'9';
 /* '9' Maximum statistical uncertainty (0.3-5%) */
 ENGY-GAMMA=(141.2KEV'40',1129.2KEV'40');
 HALF-LIFE=14.6HOUR'40';
 /* '40' Delayed gamma from 90Nb (ground state) */
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 /* Data Table                                                        */
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 \DATA;
 INC-ENGY-LAB XSECTN',41' DELTA-XSECTN'' XSECTN',42'
 DELTA-XSECTN''
 (MEV) (MB) (MB) (MB) (MB)
 22.343 2.43 +-0.18 7.60 +-0.60
 29.671 6.69 +-0.52 21.00 +-1.65
 35.8 79.68 +-6.07 87.46 +-6.68
 41.239 133.23 +-10.10 133.76 +-10.20
 46.193 119.00 +-7.00 119.18 +-9.04
 50.781 107.39 +-8.00 106.20 +-8.11
 55.055 90.39 +-6.88 90.56 +-6.92
 59.093 87.04 +-6.63 88.33 +-6.75
 62.903 90.69 +-6.90 92.53 +-7.08
 66.58 99.07 +-7.53 99.12 +-7.55
 \END;
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