2-He- 4 ENDF/B-VII.0 Processed by Red Cullen using PREPRO2007. 1 0 0 0 2004.00000 3.96821900 0 0 0 0 228 1451 1 0.0 0.0 0 0 0 6 228 1451 2 1.00000000 20000000.0 8 0 10 7 228 1451 3 0.0 0.0 1 0 119 5 228 1451 4 2-He- 4 LANL EVAL-OCT73 Nisley,Hale,Young 228 1451 5 NO PUBLICATION DIST-DEC06 228 1451 6 ----ENDF/B-VII MATERIAL 228 228 1451 7 -----INCIDENT NEUTRON DATA 228 1451 8 ------ENDF-6 FORMAT 228 1451 9 228 1451 10 **************************************************************** 228 1451 11 228 1451 12 ENDF/B-VII CONVERTED FROM ENDF/B-VI BY NNDC OCT 2004 228 1451 13 228 1451 14 **************************************************************** 228 1451 15 228 1451 16 ENDF/B-VI MOD1 Revision, January 2001, P.G. Young and 228 1451 17 S.C. Frankle (LANL) 228 1451 18 228 1451 19 The atomic weight ratio was corrected - changed from 4.0015 228 1451 20 to 3.968219. 228 1451 21 228 1451 22 **************************************************************** 228 1451 23 228 1451 24 ENDF/B-VI MOD 0, January 1990, NNDC 228 1451 25 228 1451 26 ENDF/B-V Material 1270 converted to ENDF-6 format by NNDC 228 1451 27 228 1451 28 ***************************************************************** 228 1451 29 228 1451 30 ENDF/B-V Evaluation, October 1973, R.A. Nisley, G.M. Hale, 228 1451 31 P.G. Young (LANL) 228 1451 32 228 1451 33 MF=3 ------------ SMOOTH CROSS SECTIONS ------------------------ 228 1451 34 228 1451 35 THE 2200 M/S CROSS SECTIONS ARE AS FOLLOWS, 228 1451 36 MT=1 SIGMA= 0.75916 BARNS 228 1451 37 MT=2 SIGMA= 0.75916 BARNS 228 1451 38 228 1451 39 MT=1 TOTAL CROSS SECTION 228 1451 40 SEE DISCUSSION UNDER MT=2 BELOW 228 1451 41 228 1451 42 MT=2 ELASTIC SCATTERING CROSS SECTION 228 1451 43 ALTHOUGH THE ONLY REACTION POSSIBLE FOR NEUTRONS INCIDENT 228 1451 44 ON HE-4 BELOW 20 MEV IS ELASTIC SCATTERING, THE MAJORITY 228 1451 45 OF THE N-4HE DATA IS RATHER IMPRECISE. IN ORDER TO OVER- 228 1451 46 COME THIS PROBLEM, AN R-MATRIX ANALYSIS WAS PERFORMED WITH 228 1451 47 A DATA SET WHICH INCLUDED NOT ONLY THE N-4HE DATA BUT ALSO 228 1451 48 VERY PRECISE P-4HE DATA. ALL THE AVAILABLE N-4HE AND P-4HE 228 1451 49 DATA BELOW 20 MEV WERE CONSIDERED IN THE ANALYSIS. SINCE 228 1451 50 THE PREVIOUS EVALUATION WAS COMPLETED IN 1968, SEVERAL 228 1451 51 N-4HE ELASTIC SCATTERING MEASUREMENTS HAVE BEEN DONE. THE 228 1451 52 MOST SIGNIFICANT OF THESE ARE THE LOW ENERGY NEUTRON CROSS 228 1451 53 SECTION OF RORER (RO69),THE RPI TOTAL CROSS SECTION 228 1451 54 MEASUREMENT (GO73), WHICH COVER THE RANGE EN=0.7-30 MEV, 228 1451 55 AND THE RELATIVE ANGULAR DISTRIBUTIONS OF MORGAN (MO68). 228 1451 56 A COMPLETE LIST OF REFERENCES FOR THE N-4HE DATA USED IS 228 1451 57 GIVEN BELOW. THE P-4HE DATA WAS SELECTED TO SATISFY VERY 228 1451 58 STRINGENT STATISTICAL CRITERIA AND WE BELIEVE THE POSSIBLE 228 1451 59 ERRORS OF THE PREDICTED VALUES FOR THE P-4HE SCATTERING 228 1451 60 TO BE LESS THAN 1.0 PER CENT. A SIMPLE MODEL FOR THE 228 1451 61 CHARGE DIFFERENCES BETWEEN THE N-4HE AND P-4HE SYSTEMS 228 1451 62 WAS ASSUMED AND THE N-4HE AND P-4HE DATA SETS WERE 228 1451 63 SIMULTANEOUSLY ANALYZED. THE VALUES OF THE CROSS SECTIONS 228 1451 64 AND ANGULAR DISTRIBUTIONS CONTAINED IN FILES 3 AND 4 ARE 228 1451 65 PROBABLY ACCURATE TO WITHIN 2.0 PERCENT. 228 1451 66 228 1451 67 MF=4 ------------- NEUTRON ANGULAR DISTRIBUTIONS --------------- 228 1451 68 228 1451 69 MT=2 ELASTIC SCATTERING ANGULAR DISTRIBUTIONS 228 1451 70 OBTAINED FROM THE R-MATRIX ANALYSIS DESCRIBED ABOVE 228 1451 71 UNDER MF=3,MT=2. LEGENDRE POLYNOMIAL REPRESENTATION USED. 228 1451 72 228 1451 73 ----------------------- REFERENCES------------------------------ 228 1451 74 228 1451 75 AU62 S.M.AUSTIN ET AL., PHYS.REV. 126(1962) 1532. 228 1451 76 BR72 W.B.BROSTE ET AL., PHYS.REV. C5(1972) 761. 228 1451 77 BU66 F.W.BUSSER ET AL., NUCL.PHYS. 88(1966) 593. 228 1451 78 CR72 D.S.CRAMER + L.CRANBERG, NUCL.PHYS. A180(1972) 273. 228 1451 79 FA63 U.FASOLI + G.ZAGO, NUOVO CIMENTO 30(1963) 1169. 228 1451 80 GO73 C.A.GOULDING ET AL., BULL.AM.PHYS.SOC. 18(1973) 538. 228 1451 81 HO66 B.HOOP,JR. + H.H.BARSCHALL, NUCL.PHYS. 83(1966) 65. 228 1451 82 JE66 R.W.JEWELL ET AL., PHYS.REV. 142(1966) 687. 228 1451 83 MA63 T.H.MAY ET AL., NUCL.PHYS. 45(1963) 17.(REV. MO68 + SA68) 228 1451 84 MO68 G.L.MORGAN + R.L.WALTER, PHYS.REV. 168(1968) 1114. 228 1451 85 NI71 A.NIILER ET AL., PHYS.REV. C4(1971) 36. (REV. 9/72) 228 1451 86 RO69 D.C.RORER ET AL., NUCL.PHYS. 133(1969) 410. 228 1451 87 SA68 J.R.SAWERS ET AL., PHYS.REV. 168(1968) 1102. 228 1451 88 SE53 J.D.SEAGRAVE, PHYS.REV. 92(1953) 1222. 228 1451 89 SH55 D.F.SHAW, PROC.PHYS.SOC.(LONDON) 68(1955) 43. 228 1451 90 SH64 R.E.SHAMU + J.G.JENKIN, PHYS.REV. 135(1964) B99. 228 1451 91 SM54 J.R.SMITH, PHYS.REV. 95(1954) 730. 228 1451 92 ST70 T.STAMMBACH ET AL., PHYS.REV. C2(1970) 434. 228 1451 93 WH57 R.E.WHITE + F.J.M.FARLEY, NUCL.PHYS. 3(1957) 476. 228 1451 94 YO63 P.G.YOUNG ET AL., AUST.J.PHYS. 16(1963) 185. 228 1451 95 228 1451 96 ************************ C O N T E N T S ************************ 228 1451 97 ***************** Program LINEAR (VERSION 2007-1) *************** 228 1451 98 For All Data Greater than 1.0000E-10 barns in Absolute Value 228 1451 99 Data Linearized Using Energy Dependent Uncertainty 228 1451 100 Energy Accuracy 228 1451 101 (eV) (per-cent) 228 1451 102 ----------- ----------- 228 1451 103 0.0 .010000000 228 1451 104 1.00000000 .010000000 228 1451 105 10.0000000 .100000000 228 1451 106 2.00000E+9 .100000000 228 1451 107 ***************** Program FIXUP (Version 2007-1) **************** 228 1451 108 Corrected ZA/AWR in All Sections-----------------------------Yes 228 1451 109 Corrected Thresholds-----------------------------------------No 228 1451 110 Extended Cross Sections to 20 MeV----------------------------No 228 1451 111 Allow Cross Section Deletion---------------------------------Yes 228 1451 112 Allow Cross Section Reconstruction---------------------------Yes 228 1451 113 Make All Cross Sections Non-Negative-------------------------Yes 228 1451 114 Delete Energies Not in Ascending Order-----------------------Yes 228 1451 115 Deleted Duplicate Points-------------------------------------Yes 228 1451 116 Check for Ascending MAT/MF/MT Order--------------------------Yes 228 1451 117 Check for Legal MF/MT Numbers--------------------------------Yes 228 1451 118 Allow Creation of Missing Sections---------------------------No 228 1451 119 Allow Insertion of Energy Points-----------------------------No 228 1451 120 Create Uniform Energy Grid-----------------------------------No 228 1451 121 Delete Section if Cross Section =0 at All Energies-----------Yes 228 1451 122 **************** Program DICTIN (VERSION 2007-1) **************** 228 1451 123 1 451 128 0 228 1451 124 2 151 4 0 228 1451 125 3 1 29 0 228 1451 126 3 2 29 0 228 1451 127 4 2 96 0 228 1451 128 228 1 0 129 228 0 0 130 2004.00000 3.96821900 0 0 1 0 228 2151 131 2.004000+3 1.000000+0 0 0 1 0 228 2151 132 1.000000-5 1.000000+5 0 0 0 0 228 2151 133 0.000000+0 2.457900-1 0 0 0 0 228 2151 134 228 2 0 135 228 0 0 136 2004.00000 3.96821900 0 0 0 0 228 3 1 137 0.0 0.0 0 0 1 76 228 3 1 138 76 2 228 3 1 139 1.00000E-5 .759160000 .025300000 .759160000 100.000000 .759160000 228 3 1 140 20000.0000 .758490000 60000.0000 .760030000 100000.000 .766090000 228 3 1 141 150000.000 .781580000 200000.000 .808170000 250000.000 .848990000 228 3 1 142 300000.000 .908080000 350000.000 .990590000 400000.000 1.10300000 228 3 1 143 450000.000 1.25360000 500000.000 1.45250000 550000.000 1.71140000 228 3 1 144 600000.000 2.04380000 625000.000 2.24180000 650000.000 2.46300000 228 3 1 145 675000.000 2.70870000 700000.000 2.97950000 725000.000 3.27550000 228 3 1 146 750000.000 3.59580000 775000.000 3.93860000 800000.000 4.30060000 228 3 1 147 900000.000 5.82410000 925000.000 6.18420000 950000.000 6.51800000 228 3 1 148 975000.000 6.81730000 1000000.00 7.07520000 1025000.00 7.28670000 228 3 1 149 1050000.00 7.44940000 1075000.00 7.56270000 1100000.00 7.62850000 228 3 1 150 1125000.00 7.65010000 1150000.00 7.63210000 1200000.00 7.49870000 228 3 1 151 1225000.00 7.39450000 1275000.00 7.13620000 1450000.00 6.07350000 228 3 1 152 1550000.00 5.52260000 1650000.00 5.05390000 1750000.00 4.66360000 228 3 1 153 1850000.00 4.34010000 1950000.00 4.07130000 2050000.00 3.84670000 228 3 1 154 2100000.00 3.74820000 2200000.00 3.57410000 2300000.00 3.42590000 228 3 1 155 2400000.00 3.29860000 2500000.00 3.18850000 2650000.00 3.04910000 228 3 1 156 2800000.00 2.93400000 2950000.00 2.83750000 3100000.00 2.75540000 228 3 1 157 3300000.00 2.66270000 3500000.00 2.58440000 3800000.00 2.48550000 228 3 1 158 4200000.00 2.37530000 4700000.00 2.25690000 5400000.00 2.11000000 228 3 1 159 6200000.00 1.95860000 7000000.00 1.82130000 7800000.00 1.69720000 228 3 1 160 8600000.00 1.58510000 9400000.00 1.48380000 10300000.0 1.38140000 228 3 1 161 11200000.0 1.28960000 12100000.0 1.20720000 13000000.0 1.13310000 228 3 1 162 14000000.0 1.05940000 15000000.0 .993670000 16000000.0 .935180000 228 3 1 163 17000000.0 .883190000 18100000.0 .832800000 19200000.0 .788880000 228 3 1 164 20000000.0 .760650000 228 3 1 165 228 3 0 166 2004.00000 3.96821900 0 0 0 0 228 3 2 167 0.0 0.0 0 0 1 76 228 3 2 168 76 2 228 3 2 169 1.00000E-5 .759160000 .025300000 .759160000 100.000000 .759160000 228 3 2 170 20000.0000 .758490000 60000.0000 .760030000 100000.000 .766090000 228 3 2 171 150000.000 .781580000 200000.000 .808170000 250000.000 .848990000 228 3 2 172 300000.000 .908080000 350000.000 .990590000 400000.000 1.10300000 228 3 2 173 450000.000 1.25360000 500000.000 1.45250000 550000.000 1.71140000 228 3 2 174 600000.000 2.04380000 625000.000 2.24180000 650000.000 2.46300000 228 3 2 175 675000.000 2.70870000 700000.000 2.97950000 725000.000 3.27550000 228 3 2 176 750000.000 3.59580000 775000.000 3.93860000 800000.000 4.30060000 228 3 2 177 900000.000 5.82410000 925000.000 6.18420000 950000.000 6.51800000 228 3 2 178 975000.000 6.81730000 1000000.00 7.07520000 1025000.00 7.28670000 228 3 2 179 1050000.00 7.44940000 1075000.00 7.56270000 1100000.00 7.62850000 228 3 2 180 1125000.00 7.65010000 1150000.00 7.63210000 1200000.00 7.49870000 228 3 2 181 1225000.00 7.39450000 1275000.00 7.13620000 1450000.00 6.07350000 228 3 2 182 1550000.00 5.52260000 1650000.00 5.05390000 1750000.00 4.66360000 228 3 2 183 1850000.00 4.34010000 1950000.00 4.07130000 2050000.00 3.84670000 228 3 2 184 2100000.00 3.74820000 2200000.00 3.57410000 2300000.00 3.42590000 228 3 2 185 2400000.00 3.29860000 2500000.00 3.18850000 2650000.00 3.04910000 228 3 2 186 2800000.00 2.93400000 2950000.00 2.83750000 3100000.00 2.75540000 228 3 2 187 3300000.00 2.66270000 3500000.00 2.58440000 3800000.00 2.48550000 228 3 2 188 4200000.00 2.37530000 4700000.00 2.25690000 5400000.00 2.11000000 228 3 2 189 6200000.00 1.95860000 7000000.00 1.82130000 7800000.00 1.69720000 228 3 2 190 8600000.00 1.58510000 9400000.00 1.48380000 10300000.0 1.38140000 228 3 2 191 11200000.0 1.28960000 12100000.0 1.20720000 13000000.0 1.13310000 228 3 2 192 14000000.0 1.05940000 15000000.0 .993670000 16000000.0 .935180000 228 3 2 193 17000000.0 .883190000 18100000.0 .832800000 19200000.0 .788880000 228 3 2 194 20000000.0 .760650000 228 3 2 195 228 3 0 196 228 0 0 197 2004.00000 3.96821900 0 1 0 0 228 4 2 198 0.000000+0 3.968219+0 0 2 0 0 228 4 2 199 0.000000+0 0.000000+0 0 0 1 46 228 4 2 200 46 2 228 4 2 201 0.000000+0 1.000000-5 0 0 2 0 228 4 2 202 0.000000+0 0.000000+0 228 4 2 203 0.000000+0 1.000000+0 0 0 2 0 228 4 2 204 0.000000+0 0.000000+0 228 4 2 205 0.000000+0 6.000000+4 0 0 6 0 228 4 2 206 -7.573000-2 1.531600-3-3.356700-8 6.31490-11 4.93690-12-3.18450-12 228 4 2 207 0.000000+0 1.000000+5 0 0 6 0 228 4 2 208 -1.286300-1 4.494600-3-1.580700-7 5.36690-10 9.00010-12-5.80170-12 228 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