0 4.9115E+04 1.1392E+02 0 0 0 14931 1451 1 0.0000E+00 0.0000E+00 0 0 0 64931 1451 2 1.0000E+00 0.0000E+00 0 0 10 64931 1451 3 0.0000E+00 0.0000E+00 0 0 84 54931 1451 4 49-IN-115 CNDC/CIAE EVAL-JUN91 CAI DUNJIU AND WANG ZISHENG 4931 1451 5 ---ENDF-6 FORMAT 4931 REVISION 0 4931 1451 6 4931 1451 7 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 4931 1451 8 4931 1451 9 Evaluation of the 115-In(n,2n) 114m-In Reaction 4931 1451 10 Cross-section 4931 1451 11 Cai Dunjiu Yu Baosheng Wang Zisheng 4931 1451 12 Lu Hanlin Zhao Wenrong 4931 1451 13 Institute of Atomic Energy, China 4931 1451 14 The excitation function of 115-In(n, 2n) 114m-In reaction 4931 1451 15 covers neutron energy range from threshold of 9.228 MeV 4931 1451 16 ( including the energy of isomeric state which has 4931 1451 17 0.190 MeV ) to 20 MeV. Experimental knowledge of the 4931 1451 18 115-In(n,2n) reaction cross sections is entirely based 4931 1451 19 on the results of activation measurements. There are 4931 1451 20 still no experimental results obtained by 4931 1451 21 direct-neutron-detection methods (such as scintillation 4931 1451 22 tank). For both the indium isotopes (115-In,0.957, 4931 1451 23 113-In,0.043), the primary activity 4931 1451 24 resulting from the (n,2n) process is due to the decay of 4931 1451 25 metastable state. The interaction with the primary isotope, 4931 1451 26 115-In, results in a metastable state in 114-In which 4931 1451 27 decays with 49.5d half-life by means of an E4 transition 4931 1451 28 to the ground state (1+) with a half-life of 71.9s. 4931 1451 29 The (n,2n) process also directly populates the ground state. 4931 1451 30 Seventeen sets of data available [1-18] were collected. 4931 1451 31 For the sake of comparison, all the experimental results were 4931 1451 32 adjusted by the unified nuclear parameters (including 4931 1451 33 intensity of r-line, half-life, branching ratio), 4931 1451 34 the reference cross section and the dependence of cross 4931 1451 35 section on energy which were taken from [Ref.1]. In several 4931 1451 36 cases, adjustments were made only for the dependence of cross 4931 1451 37 section on energy since some necessary parameters used in data 4931 1451 38 analysis were not given by the authors. 4931 1451 39 The evaluation was made as the following ways: 4931 1451 40 (1).At 14.7MeV neutron energy . 4931 1451 41 Based on the results measured by Ge(Li) detector,the 4931 1451 42 recommended cross section at 14.7 MeV is 1290 mb. 4931 1451 43 (2). For the neutron energy range from threshold to 20 MeV. 4931 1451 44 The recommended excitation function was obtained 4931 1451 45 by fitting the measured data with least-square method in the 4931 1451 46 neutron energy range of 10.4-20MeV and by extrapolating from 4931 1451 47 10.4MeV to 9.228MeV based on the physical trend and systematics 4931 1451 48 calculation. 4931 1451 49 Covariance matrix is given for the evaluated data considering all 4931 1451 50 adjusted factors. 4931 1451 51 References 4931 1451 52 1.Zhao Wenrong et al., CNDC-89014;INDC(CPR)-16, 1989 4931 1451 53 2.Ke Wei et al., Chin.J.Nucl.Phys.11, 3, 11(1989) 4931 1451 54 Lu Hanlin et al., INDC(CPR)-011/GI, P67(1988) 4931 1451 55 3.J.Csikai et al., INDC(NDS)-232/L, P45(1989) 4931 1451 56 4.Li Jiangwei et al., Chin.J.Nucl.Phys., 10, 1, 52(1988) 4931 1451 57 Wu Zhihua et al., 88MITO, P315(1988) 4931 1451 58 5.T.B.Ryves et al., J.Phys., G9, 1549(1983) 4931 1451 59 6.T.B.Ryves et al., J.Phys., G7, 115(1981) 4931 1451 60 7.A.Reggoug et al., 82Antwerp, P873(1982);NIMA, 227, 249(1984) 4931 1451 61 8.K.Kayashima et al., NEANDC(J)-61U, P94(1979) 4931 1451 62 9.D.C.Santry et al., Can.J.Phys., 54, 757(1976) 4931 1451 63 10.Lu Hanlin et al., At.Energy Sci.Technol., 2, 113(1975) 4931 1451 64 11.A.Paulsen et al., Atomkernenergie, 26, 34(1975) 4931 1451 65 12.J.K.Temperley et al., BRL-1491(1970) 4931 1451 66 13.R.C.Barrall et al., Nucl.Phys., A138, 387(1969) 4931 1451 67 14.R.C.Barrall et al., AFWL-TR-68-134(1969) 4931 1451 68 15.H.Rotzer, Nucl.Phys., A109, 694(1968);DWA176, 289(1968) 4931 1451 69 16.B.Minetti et al., Z.Physik., A217, 83(1968) 4931 1451 70 17.H.O.Menlove et al., Phys.Rev., 163, 1308(1967) 4931 1451 71 18.R.J.Prestwood et al., Phys.Rev., 121, 1438(1961) 4931 1451 72 19.T.Kozlowski et al., Acta.Phys.Pol., 33, 409(1968) 4931 1451 73 20.R.Prasad et al.,Nucl.Phys., A94, 476(1967) 4931 1451 74 and 88,349(1966). 4931 1451 75 21.W.Nagel, JNE, 20, 475(1966) 4931 1451 76 22.K.C.Garg et al.,IPA17, 525(1979) 4931 1451 77 23.G.N.Salaita et al., ANS, 16, 59(1973) 4931 1451 78 24.J.Janczyszyn et al., J.Radiational Chem., 14, 201(1973) 4931 1451 79 25.M.Bormann et al., EANDC(E)76u, 51(1967) 4931 1451 80 26.W.Grochulski et al., INR-1172(1970);INR-1197, 10(1970) 4931 1451 81 Acta.Phys.Pol., BI, 271(1970) 4931 1451 82 27.H.K.Vonach et al., 68WASH, 2, P885(1968) 4931 1451 83 28.Wang Zisheng et al., Research on the Covariances Matrix 4931 1451 84 of the Evaluation Data(to be published) 4931 1451 85 4931 1451 86 4931 1451 87 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 4931 1451 88 1 451 93 14931 1451 89 2 151 4 14931 1451 90 8 16 4 14931 1451 91 10 16 22 14931 1451 92 40 16 24 14931 1451 93 4931 1 0 94 4931 0 0 95 4.9115E+04 1.1392E+02 0 0 1 04931 2151 96 4.9115E+04 1.0000E+00 0 0 1 04931 2151 97 1.0000E-05 2.0000E+07 0 0 0 04931 2151 98 4.5000E+00 6.5500E-01 0 0 0 04931 2151 99 0.0000E+00 0.0000E+00 0 0 0 04931 2 0 100 0.0000E+00 0.0000E+00 0 0 0 04931 0 0 101 4.9115E+04 1.1392E+02 0 0 1 04931 8 16 102 4.9114E+04 1.9000E+05 10 1 12 49314931 8 16 103 1.7820E+05 3.0000E+00 4.9114E+04 9.5600E-01 1.9000E+05 2.0000E+004931 8 16 104 1.7820E+05 2.0000E+00 4.8114E+04 4.4000E-02 5.8900E+06 2.0000E+004931 8 16 105 4931 8 0 106 4931 0 0 107 4.9115E+04 1.1392E+02 0 0 1 0493110 16 108 -9.0350E+06-9.2250E+06 0 1 1 55493110 16 109 55 2 493110 16 110 9.3060E+06 0.0000E+00 9.4000E+06 7.7320E-03 9.6000E+06 2.5000E-02493110 16 111 9.8000E+06 8.0130E-02 1.0000E+07 1.4610E-01 1.0200E+07 2.2880E-01493110 16 112 1.0400E+07 3.1410E-01 1.0600E+07 4.0790E-01 1.0800E+07 4.8820E-01493110 16 113 1.1000E+07 5.6490E-01 1.1200E+07 6.3790E-01 1.1400E+07 7.0710E-01493110 16 114 1.1600E+07 7.7260E-01 1.1800E+07 8.3420E-01 1.2000E+07 8.9200E-01493110 16 115 1.2200E+07 9.4600E-01 1.2400E+07 9.9610E-01 1.2600E+07 1.0420E+00493110 16 116 1.2800E+07 1.0850E+00 1.3000E+07 1.1240E+00 1.3200E+07 1.1580E+00493110 16 117 1.3400E+07 1.1900E+00 1.3600E+07 1.2170E+00 1.3800E+07 1.2410E+00493110 16 118 1.4000E+07 1.2620E+00 1.4200E+07 1.2790E+00 1.4400E+07 1.2930E+00493110 16 119 1.4600E+07 1.3030E+00 1.4800E+07 1.3110E+00 1.5000E+07 1.3150E+00493110 16 120 1.5200E+07 1.3170E+00 1.5400E+07 1.3160E+00 1.5600E+07 1.3130E+00493110 16 121 1.5800E+07 1.3070E+00 1.6000E+07 1.2990E+00 1.6200E+07 1.2920E+00493110 16 122 1.6400E+07 1.2860E+00 1.6600E+07 1.2800E+00 1.6800E+07 1.2740E+00493110 16 123 1.7000E+07 1.2690E+00 1.7200E+07 1.2630E+00 1.7400E+07 1.2570E+00493110 16 124 1.7600E+07 1.2540E+00 1.7800E+07 1.2460E+00 1.8000E+07 1.2390E+00493110 16 125 1.8200E+07 1.2300E+00 1.8400E+07 1.2200E+00 1.8600E+07 1.2060E+00493110 16 126 1.8800E+07 1.1930E+00 1.9000E+07 1.1780E+00 1.9200E+07 1.1590E+00493110 16 127 1.9400E+07 1.1460E+00 1.9600E+07 1.1270E+00 1.9800E+07 1.1120E+00493110 16 128 2.0000E+07 1.1030E+00 493110 16 129 493110 0 130 4931 0 0 131 4.9115E+04 1.1392E+02 0 0 1 0493140 16 132 -9.0350E+06-9.2250E+06 0 0 0 1493140 16 133 1.0000E+01 0.0000E+00 0 16 0 1493140 16 134 0.0000E+00 0.0000E+00 1 5 120 15493140 16 135 1.0000E-05 1.0000E+07 1.0500E+07 1.1500E+07 1.2200E+07 1.2700E+07493140 16 136 1.3200E+07 1.3800E+07 1.4200E+07 1.4700E+07 1.5200E+07 1.6000E+07493140 16 137 1.7200E+07 1.8000E+07 2.0000E+07 4.0000E-01 1.1545E-02 2.8867E-03493140 16 138 5.2075E-04 6.2687E-04 2.6340E-04 7.5764E-05 0.0000E+00 0.0000E+00493140 16 139 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 1.3605E-03493140 16 140 2.3293E-04 4.3793E-05 3.3139E-05 2.3757E-05 6.4294E-06 0.0000E+00493140 16 141 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00493140 16 142 4.2732E-04 5.1490E-05 5.6717E-05 3.9702E-05 1.6118E-05 0.0000E+00493140 16 143 5.1340E-06 5.3301E-06 0.0000E+00 3.8509E-06 2.7558E-07 0.0000E+00493140 16 144 1.3261E-04 7.0264E-05 5.0570E-05 1.8140E-05 1.0258E-05 1.0919E-05493140 16 145 1.1519E-05 6.0543E-06 4.0322E-06 3.1830E-06 2.5770E-07 1.0616E-04493140 16 146 7.1939E-05 1.8277E-05 7.8061E-06 1.0639E-05 1.1951E-05 9.6235E-06493140 16 147 6.6197E-06 5.0638E-06 1.3004E-06 9.3808E-05 2.0023E-05 8.7883E-06493140 16 148 1.2120E-05 1.3490E-05 1.0628E-05 7.7045E-06 6.6884E-06 1.4738E-06493140 16 149 5.1456E-05 2.2704E-05 1.4361E-05 1.6860E-05 4.7152E-06 4.4527E-06493140 16 150 4.2332E-06 1.2007E-06 4.8049E-05 1.2322E-05 1.3478E-05 3.7659E-06493140 16 151 2.7570E-06 3.3884E-06 4.4054E-07 4.7071E-05 2.1340E-05 8.5659E-06493140 16 152 1.5785E-05 9.7195E-06 9.1197E-06 4.5801E-05 1.3853E-05 1.1545E-05493140 16 153 1.7545E-05 3.1561E-06 4.5547E-05 1.3366E-05 2.4694E-05 2.7245E-06493140 16 154 4.6225E-05 2.2176E-05 1.3748E-05 7.8988E-05 5.9268E-06 8.0124E-05493140 16 155 493140 0 156 4931 0 0 157 0 0 0 158 -1 0 0 159