Retrieved by E4-util: 2010/06/03,20:03:36 1 0 0 0 2.003000+3 2.990120+0 0 0 6 1 225 1451 1 0.000000+0 0.000000+0 0 0 0 6 225 1451 2 1.000000+0 6.000000+7 0 0 10 4 225 1451 3 0.000000+0 0.000000+0 0 0 160 10 225 1451 4 2-He- 3 JAERI EVAL-JUN87 K.SHIBATA 225 1451 5 JAERI-M 90-024 DIST-MAY10 20090827 225 1451 6 ----JENDL-4 MATERIAL 225 225 1451 7 -----INCIDENT NEUTRON DATA 225 1451 8 ------ENDF-6 FORMAT 225 1451 9 225 1451 10 **************************************************************** 225 1451 11 FENDL-3 ad-hoc extension to 60 MeV 225 1451 12 (A. Trkov for the IAEA-NDS, October 2011) 225 1451 13 225 1451 14 The requirement of the FENDL-3 library is to have the evaluations 225 1451 15 for all relevant materials extending to at least 60 MeV. Since 225 1451 16 there are no available evaluations that would meet these 225 1451 17 requirements, an ad-hoc extension was made. 225 1451 18 225 1451 19 Total cross section 225 1451 20 The data of Haesner [1], Goulding [2] and Battat [3] were 225 1451 21 considered. The total cross section is the sum of the partials. 225 1451 22 The constituent reaction cross sections (mainly the elastic), 225 1451 23 were adjusted such that the total cross section matched the 225 1451 24 bulk of the experimental points. 225 1451 25 225 1451 26 Elastic cross section 225 1451 27 The competing reactions (n,p) and (n,d) are small. The elastic 225 1451 28 cross sections were extrapolated linearly on log-log scale with 225 1451 29 a gradient adjusted to match the measured total cross sections. 225 1451 30 Experimental data for the elastic cross sections above 20 MeV by 225 1451 31 Haesner [1] are available in EXFOR, but they seem to be strongly 225 1451 32 underestimated and are inconsistent with the measured total 225 1451 33 cross sections, so they are ignored. 225 1451 34 225 1451 35 Elastic angular distributions 225 1451 36 Above 20 MeV measurements of the elastic angular differential 225 1451 37 cross section by Haesner [1] are available and they extend up 225 1451 38 to 30 MeV. The angular distributions in the JENDL-4 evaluation 225 1451 39 are in good agreement with the measurements. Some systematic 225 1451 40 discrepancy is due to the underestimation of the elastic cross 225 1451 41 section. A flat extrapolation to 60 MeV was performed. 225 1451 42 225 1451 43 Non-elastic cross section 225 1451 44 The non-elastic cross section is redundant and can be 225 1451 45 reconstructed from the cross sections of the constituting 225 1451 46 reactions. It is sometimes needed to describe the gamma-emission 225 1451 47 data, but this is not the case for 3He. Therefore, the reaction 225 1451 48 was deleted from the original file. 225 1451 49 225 1451 50 Radiative capture cross section 225 1451 51 The radiative capture cross sections in the JENDL-4 library 225 1451 52 differ considerably from those in the ENDF/B-VII.1b4 library, 225 1451 53 which tend to be supported by the data of Komar and some other 225 1451 54 measurements, which are not in EXFOR. It is possible that the 225 1451 55 ENDF/B-VII.1b4 data are closer to the truth for this reaction 225 1451 56 in this energy region, but for the sake of consistency the 225 1451 57 JENDL-4 cross sections are retained. Extrapolation to 60 MeV 225 1451 58 is done assuming approximately a 1/v shape. 225 1451 59 225 1451 60 Proton emission cross section 225 1451 61 The proton emission cross section in JENDL-4 follows the data 225 1451 62 of Haesner [1] near 20 MeV. The same experimental data extend 225 1451 63 to 30 MeV. Extrapolation to 60 MeV is performed assuming linear 225 1451 64 behaviour in log-log scale with a gradient to match the Haesner 225 1451 65 data. No emission spectra or angular distributions of protons 225 1451 66 are given. 225 1451 67 225 1451 68 Deuteron emission cross section 225 1451 69 Deuteron emission cross section has a threshold at 4.36 MeV. 225 1451 70 Above 10 MeV the data of Haesner [1] are available. The 225 1451 71 JENDL-4 evaluation seems to follow the data better than the 225 1451 72 ENDF/B-VII.1b4 evaluation. The measured data are available 225 1451 73 up to 30 MeV. Extrapolation to 60 MeV is performed assuming 225 1451 74 linear behaviour in log-log scale with a gradient to match 225 1451 75 the Haesner data. No emission spectra or angular distributions 225 1451 76 of deuterons are given. 225 1451 77 225 1451 78 =========================================================== 225 1451 79 The data were taken from JENDL-3.3. 225 1451 80 =========================================================== 225 1451 81 225 1451 82 225 1451 83 =========================================================== 225 1451 84 JENDL-3.2 data were automatically transformed to JENDL-3.3. 225 1451 85 Interpolation of spectra: 22 (unit base interpolation) 225 1451 86 (3,251) deleted, T-matrix of (4,2) deleted, and others. 225 1451 87 =========================================================== 225 1451 88 225 1451 89 HISTORY 225 1451 90 87-06 NEWLY EVALUATED BY K.SHIBATA 225 1451 91 94-01 MODIFIED BY K.SHIBATA FOR JENDL-3.2 225 1451 92 **** MODIFIED PARTS FOR JENDL-3.2 ************************* 225 1451 93 (3,102),(12,102),(14,102) ADDED 225 1451 94 (3,3) CALCULATED 225 1451 95 (3,1) SUM OF PARTIAL CROSS SECTIONS 225 1451 96 ************************************************************* 225 1451 97 MF=1 GENERAL INFORMATION 225 1451 98 MT=451 DESCRIPTIVE DATA 225 1451 99 225 1451 100 MF=2 RESONANCE PARAMETERS 225 1451 101 MT=151 SCATTERING RADIUS ONLY 225 1451 102 225 1451 103 MF=3 NEUTRON CROSS SECTIONS 225 1451 104 CALCULATED 2200M/S CROSS SECTIONS AND RES. INTEGRALS 225 1451 105 2200M/S (B) RES.INTEG (B) 225 1451 106 TOTAL 5331.1 - 225 1451 107 ELASTIC 3.135 - 225 1451 108 CAPTURE 5.401E-5 2.4691E-4 225 1451 109 (N,P) 5328.0 - 225 1451 110 225 1451 111 MT=1 TOTAL 225 1451 112 BELOW 1 MEV, THE EXPERIMENTAL DATA /1/ WERE ANALYZED USING 225 1451 113 THE R-MATRIX THEORY. 225 1451 114 ABOVE 1 MEV, BASED ON EXPERIMENTAL DATA /2-4/. 225 1451 115 MT=2 ELASTIC 225 1451 116 BELOW 1 MEV, THE EXPERIMENTAL DATA /1/ WERE ANALYZED USING 225 1451 117 THE R-MATRIX THEORY. 225 1451 118 ABOVE 1 MEV, (ELASTIC) = (TOTAL) - (NON ELASTIC) 225 1451 119 MT=3 NON-ELASTIC 225 1451 120 SUM OF (3,102), (3,103) AND (3,104) 225 1451 121 MT=102 CAPTURE 225 1451 122 S- AND P-WAVE CAPTURE, BASED ON EXPERIMENTAL DATA /5,6,7/. 225 1451 123 MT=103 (N,P) 225 1451 124 BELOW 1 MEV, THE EXPERIMENTAL DATA /8/ WERE ANALYZED USING 225 1451 125 THE R-MATRIX THEORY. 225 1451 126 ABOVE 1 MEV, BASED ON EXPERIMENTAL DATA /9,10/. 225 1451 127 MT=104 (N,D) 225 1451 128 EVALUATION WAS PERFORMED ON THE BASIS OF EXPERIMENTAL 225 1451 129 DATA /9,10/. 225 1451 130 MT=251 MU-BAR 225 1451 131 CALCULATED FROM THE DATA IN FILE-4. 225 1451 132 225 1451 133 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 225 1451 134 MT=2 ELASTIC 225 1451 135 BASED ON THE FOLLOWING EXPERIMENTAL DATA: 225 1451 136 1.0E-5 EV TO 500 KEV : ISOTROPIC IN C.M. 225 1451 137 1.0, 2.0, 3.5 MEV : SEAGRAVE ET AL. /11/ 225 1451 138 5 TO 20 MEV : HAESNER /9/ 225 1451 139 225 1451 140 MF=12 PHOTON PRODUCTION MULTIPLICITY 225 1451 141 MT=102 CAPTURE 225 1451 142 M=1.0 FOR THE TRANSITION TO G.S OF HE-4. 225 1451 143 225 1451 144 MF=14 PHOTON ANGULAR DISTRIBUTION 225 1451 145 MT=102 CAPTURE 225 1451 146 ASSUMED TO BE ISOTROPIC. 225 1451 147 225 1451 148 REFERENCES 225 1451 149 1) ALFIMENKOV V.P. ET AL.: YAD. FIZ., 33, 891 (1981), TRANSLATION 225 1451 150 SOV. J. NUCL. PHYS., 33, 467 (1981). 225 1451 151 2) LOS ALAMOS PHYSICS AND CRYOGENICS GROUPS: NUCL. PHYS., 12, 225 1451 152 291 (1959). 225 1451 153 3) GOULDING C.A. ET AL.: NUCL. PHYS., A215, 253 (1973). 225 1451 154 4) HAESNER B. ET AL.: PHYS. REV., C28, 995 (1983). 225 1451 155 5) WOLFS F.L.H. ET AL.: PHYS. REV. LETT., 63, 2721 (1989). 225 1451 156 6) WELVELMAN R. ET AL.: NUCL. SCI. ENG., 102, 428 (1989). 225 1451 157 7) WARD L. ET AL.: PHYS. REV., C24, 317 (1981). 225 1451 158 8) BORZAKOV S.B. ET AL.: YAD. FIZ., 35, 532 (1982), TRANSLATION 225 1451 159 SOV. J. NUCL. PHYS., 35, 307 (1982). 225 1451 160 9) HAESNER B.: KFK-3395 (1982). 225 1451 161 10) DROSG M.: DEDUCED FROM INVERSE REACTION, LA-7269-MS (1978). 225 1451 162 11) SEAGRAVE J.D. ET AL.: PHYS. REV., 119, 1981 (1961). 225 1451 163 225 1451 164 1 451 174 1 225 1451 165 2 151 4 0 225 1451 166 3 1 105 0 225 1451 167 3 2 70 0 225 1451 168 3 102 14 0 225 1451 169 3 103 61 0 225 1451 170 3 104 21 0 225 1451 171 4 2 38 0 225 1451 172 12 102 4 0 225 1451 173 14 102 1 0 225 1451 174 0.000000+0 0.000000+0 0 0 0 0 225 1 099999 0.000000+0 0.000000+0 0 0 0 0 225 0 0 0 2.003000+3 2.990120+0 0 0 1 0 225 2151 1 2.003000+3 1.000000+0 0 0 1 0 225 2151 2 1.000000-5 1.000000+6 0 0 0 0 225 2151 3 5.000000-1 3.000000-1 0 0 0 0 225 2151 4 0.000000+0 0.000000+0 0 0 0 0 225 2 099999 0.000000+0 0.000000+0 0 0 0 0 225 0 0 0 2.003000+3 2.990120+0 0 0 0 0 225 3 1 1 0.000000+0 0.000000+0 0 0 1 304 225 3 1 2 304 2 225 3 1 3 1.000000-5 2.680630+5 1.281250-5 2.368210+5 1.562500-5 2.144510+5 225 3 1 4 2.125000-5 1.838910+5 2.687500-5 1.635180+5 3.250000-5 1.486960+5 225 3 1 5 4.375000-5 1.281600+5 5.500000-5 1.143040+5 6.625000-5 1.041480+5 225 3 1 6 7.750000-5 9.629310+4 1.000000-4 8.477110+4 1.386710-4 7.198730+4 225 3 1 7 1.773430-4 6.365640+4 2.160150-4 5.767770+4 2.546870-4 5.311870+4 225 3 1 8 3.320310-4 4.652250+4 4.093750-4 4.189810+4 5.640620-4 3.569390+4 225 3 1 9 7.187500-4 3.162080+4 8.734350-4 2.868460+4 1.000000-3 2.680810+4 225 3 1 10 1.028120-3 2.643900+4 1.337500-3 2.318040+4 1.646870-3 2.089010+4 225 3 1 11 1.956250-3 1.916730+4 2.575000-3 1.670660+4 3.193750-3 1.500140+4 225 3 1 12 3.812500-3 1.373030+4 5.050000-3 1.193020+4 6.287500-3 1.069210+4 225 3 1 13 7.525000-3 9.773670+3 1.000000-2 8.478630+3 1.382500-2 7.211200+3 225 3 1 14 1.765000-2 6.382360+3 2.147500-2 5.786290+3 2.530000-2 5.331130+3 225 3 1 15 3.463750-2 4.556450+3 4.397500-2 4.044050+3 5.331250-2 3.673030+3 225 3 1 16 6.265000-2 3.388420+3 8.132500-2 2.974290+3 1.000000-1 2.682430+3 225 3 1 17 1.281250-1 2.369920+3 1.562500-1 2.146160+3 2.125000-1 1.840520+3 225 3 1 18 2.687500-1 1.636800+3 3.250000-1 1.488590+3 4.375000-1 1.283270+3 225 3 1 19 5.500000-1 1.144750+3 6.625000-1 1.043230+3 7.750000-1 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