IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 1.60320E+4 3.16974E+1 0 0 1 11630 1451 1 0.0 0.0 0 0 0 01630 1451 2 0.0 0.0 0 0 97 41630 1451 3 16-S - 32 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.1630 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 1630 1451 5 IDENTIFIER=INDL 1630 REV1 1630 1451 6 FORMAT= ENDF/B-5 1630 1451 7 ================================================================= 1630 1451 8 1630 1451 9 ======================= For MT = 16 ======================== 1630 1451 10 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 1630 1451 11 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 1630 1451 12 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 1630 1451 13 TEXT= 1630 1451 14 16-S-32(N,2N)16-S-31 EN.REG. UP TO 20.MEV IN STEPS OF 100.KEV 1630 1451 15 16-S-32(N,P)15-P-32 EN.REG. UP TO 20.MEV IN STEPS OF 100.KEV 1630 1451 16 16-S-32(N,T)15-P-30 EN.REG. UP TO 20.MEV IN STEPS OF 100.KEV 1630 1451 17 16-S-32(N,A)14-SI-29 EN.REG. UP TO 20.MEV IN STEPS OF 100.KEV 1630 1451 18 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 1630 1451 19 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 1630 1451 20 OBNINSK,USSR). 1630 1451 21 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 1630 1451 22 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 1630 1451 23 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 1630 1451 24 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 1630 1451 25 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 1630 1451 26 KONSTANTY,32(1),PAGE 105,1979 1630 1451 27 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 1630 1451 28 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 1630 1451 29 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 1630 1451 30 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 1630 1451 31 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 1630 1451 32 YAD. KOSTANTY 3,(42),P.60,(1981) 1630 1451 33 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.1630 1451 34 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 1630 1451 35 REACTION | V.2,P.271,IAEA,VIENNA) 1630 1451 36 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 1630 1451 37 -------------|-------------|---------------|------------------ 1630 1451 38 16-S-32(N,2N) | 0.63E-05 | 0.48E-05 | 1.18E-05 1630 1451 39 16-S-32(N,P) | 65.6 | 64.5 | 61.9 1630 1451 40 16-S-32(N,T) | 1.06E-05 | 0.8E-05 | 1.8E-05 1630 1451 41 16-S-32(N,A) | 43.6 | 42.8 | 41.2 1630 1451 42 ================================================================= 1630 1451 43 1630 1451 44 ======================= For MT = 103 ======================== 1630 1451 45 1.60320+ 4 3.16974+ 1 0 0 0 11630 1451 46 0.0 + 0 0.0 + 0 0 0 0 01630 1451 47 0.0 + 0 0.0 + 0 0 0 32 31630 1451 48 16-S - 32 BNL EVAL-APR79 DIVADEENAM 1630 1451 49 DIST-AUG79 810730 1630 1451 50 FILE- 3 - NEUTRON INDUCED CROSS SECTIONS 1630 1451 51 --------------------------------------------------- 1630 1451 52 MT = 103---(N,P) CROSS SECTION ****************** 1630 1451 53 EXPERIMENTAL DATA EXTENDING FROM 1.6 MEV TO 20.0 MEV 1630 1451 54 WAS EVALUATED(REFS. 1-15). ALLEN'S DATA ON 32S(N,P) 1630 1451 55 WERE RENORMALIZED TO THE ENDF/B V 238(N,F) CROSS 1630 1451 56 SECTION VALUES. 1630 1451 57 *** **** **** **** **** ***** ***** ***** 1630 1451 58 REFERENCES 1630 1451 59 ---------- 1630 1451 60 --------(N,P) CROSS SECTION----- 1630 1451 61 1. SEPPI, THESIS,UNIV. OF IDAHO(1956) 1630 1451 62 2. WESTERMARK,PHYS. REV.88, 23(1952). 1630 1451 63 3. DUDLEY AND KENNERLEY, IN ENDF/B-IV DOSIMETRY FILE, 1630 1451 64 BNL-NCS-50446, EDITED BY MAGURNO 1630 1451 65 4. BARRAL ET.AL., AFWL-TR-68-134(1969)AND NUCL.PHYS. 1630 1451 66 A138,387(1969). 1630 1451 67 5. PASQUARELLI, NUCL.PHYS.A93,218(1967) 1630 1451 68 6. KHURANA ET.AL., NUCL.PHYS. 69,153(1965) 1630 1451 69 7. SANTRY ET. AL., CAN J. CHEM, 41,123,(1963) 1630 1451 70 8. LEVKOSKII, ZH. EKSP. TEOR. FIZ., 45,305(1963) 1630 1451 71 9. ALLAN, NUCL. PHYS. 24, 274(1961) 1630 1451 72 10. ALLEN JR. ET. AL., PHYS. REV.107,1368(1957) 1630 1451 73 11. HURLIMANN, ET. AL., HELV. PHYS. ACTA, 28, 33(1955) 1630 1451 74 12. LUSCHER ET. AL., HELV. PHYS. ACTA, 23,561(1950) 1630 1451 75 13. PAUL ET.AL., CAN. J. PHYS. 31,267(1953) 1630 1451 76 14. KLEMA ET.AL., PHYS. REV. 106,(1948) 1630 1451 77 15. ANTOLKOVIC,NUCL.PHYS. 44,123(1963) 1630 1451 78 ***************** PROGRAM LINEAR (VERSION 82-1) *****************1630 1451 79 DATA LINEARIZED USING A MAXIMUM ERROR OF 0.100 PER-CENT 1630 1451 80 1630 1451 81 ================================================================= 1630 1451 82 ***************** Program LINEAR (VERSION 2002-1) ***************1630 1451 83 For All Data Greater than 1.0000E-10 barns in Absolute Value 1630 1451 84 Data Linearized to Within an Accuracy of .100000000 per-cent 1630 1451 85 ***************** Program FIXUP (Version 2002-1) ****************1630 1451 86 Corrected ZA/AWR in All Sections-----------------------------Yes 1630 1451 87 Corrected Thresholds-----------------------------------------Yes 1630 1451 88 Extended Cross Sections to 20 MeV----------------------------No 1630 1451 89 Allow Cross Section Deletion---------------------------------No 1630 1451 90 Allow Cross Section Reconstruction---------------------------No 1630 1451 91 Make All Cross Sections Non-Negative-------------------------Yes 1630 1451 92 Delete Energies Not in Ascending Order-----------------------Yes 1630 1451 93 Deleted Duplicate Points-------------------------------------Yes 1630 1451 94 Check for Ascending MAT/MF/MT Order--------------------------Yes 1630 1451 95 Check for Legal MF/MT Numbers--------------------------------Yes 1630 1451 96 Allow Creation of Missing Sections---------------------------No 1630 1451 97 Allow Insertion of Energy Points-----------------------------No 1630 1451 98 Create Uniform Energy Grid-----------------------------------No 1630 1451 99 Delete Section if Cross Section =0 at All Energies-----------Yes 1630 1451 100 1 451 104 11630 1451 101 3 16 10 11630 1451 102 3 103 27 11630 1451 103 33 103 13 11630 1451 104 1630 1 0 105 1630 0 0 106 1.60320E+4 3.16974E+1 0 0 0 01630 3 16 107 2.93000E+2-1.50800E+7 0 0 1 211630 3 16 108 21 2 1630 3 16 109 15555748.8 0.0 15600000.0 0.0 15700000.0 3.00000E-51630 3 16 110 15800000.0 7.00000E-5 15900000.0 .000120000 16000000.0 .0001500001630 3 16 111 16400000.0 .000355200 17000000.0 .000660000 17200000.0 .0007720001630 3 16 112 17400000.0 .000878000 17600000.0 .000978000 17800000.0 .0010720001630 3 16 113 18000000.0 .001160000 18300000.0 .001280000 18500000.0 .0013520001630 3 16 114 18700000.0 .001420000 19000000.0 .001510000 19300000.0 .0015870001630 3 16 115 19600000.0 .001652000 19900000.0 .001705000 20000000.0 .0017200001630 3 16 116 1630 3 0 117 1.60320E+4 3.16974E+1 0 99 0 01630 3103 118 0.0 -9.27500E+5 0 0 1 701630 3103 119 70 2 1630 3103 120 956761.075 0.0 1000000.00 1.28000E-5 1100000.00 2.50000E-51630 3103 121 1200000.00 5.00000E-5 1300000.00 .000112000 1400000.00 .0002300001630 3103 122 1500000.00 .000470000 1600000.00 .000950000 1700000.00 .0018000001630 3103 123 1800000.00 .004000000 1900000.00 .007800000 2000000.00 .0145000001630 3103 124 2100000.00 .029500000 2200000.00 .052000000 2300000.00 .0840000001630 3103 125 2350000.00 .094000000 2400000.00 .086500000 2500000.00 .0730000001630 3103 126 2600000.00 .079000000 2700000.00 .066000000 2800000.00 .1290000001630 3103 127 2900000.00 .100000000 3000000.00 .137000000 3100000.00 .1840000001630 3103 128 3200000.00 .134000000 3250000.00 .140000000 3300000.00 .2000000001630 3103 129 3350000.00 .223000000 3400000.00 .210000000 3450000.00 .2050000001630 3103 130 3500000.00 .212000000 3600000.00 .264000000 3700000.00 .2100000001630 3103 131 3800000.00 .166000000 3900000.00 .185000000 4000000.00 .3000000001630 3103 132 4100000.00 .338000000 4300000.00 .370000000 4400000.00 .3300000001630 3103 133 4600000.00 .280000000 4800000.00 .262000000 5000000.00 .2580000001630 3103 134 5200000.00 .260000000 5400000.00 .280000000 5600000.00 .3200000001630 3103 135 5800000.00 .330000000 6000000.00 .336000000 6500000.00 .3400000001630 3103 136 7000000.00 .341000000 7500000.00 .344000000 8000000.00 .3500000001630 3103 137 8500000.00 .358000000 9000000.00 .371000000 9500000.00 .3900000001630 3103 138 10000000.0 .416000000 10500000.0 .430000000 11000000.0 .4320000001630 3103 139 11500000.0 .426000000 12000000.0 .388000000 12500000.0 .3380000001630 3103 140 13000000.0 .308000000 13500000.0 .280000000 14000000.0 .2530000001630 3103 141 14500000.0 .225000000 15000000.0 .210000000 16000000.0 .1640000001630 3103 142 17000000.0 .127000000 18000000.0 .101000000 19000000.0 .0870000001630 3103 143 20000000.0 .077000000 1630 3103 144 1630 3 0 145 1630 0 0 146 1.60320E+4 3.16974E+1 0 0 0 1163033103 147 0.00000+ 0 0.00000+ 0 0 103 0 2163033103 148 0.00000+ 0 0.00000+ 0 0 1 20 10163033103 149 1.00000- 5 0.00000+ 0 1.50000+ 6 1.10000- 2 3.50000+ 6 8.00000- 3163033103 150 4.50000+ 6 8.00000- 3 5.50000+ 6 4.00000- 3 8.00000+ 6 8.00000- 3163033103 151 1.10000+ 7 1.00000- 2 1.40000+ 7 4.00000- 3 1.70000+ 7 4.00000- 3163033103 152 2.00000+ 7 0.00000+ 0 163033103 153 0.00000+ 0 0.00000+ 0 0 1 28 14163033103 154 1.00000- 5 0.00000+ 0 1.50000+ 6 1.10000- 2 2.50000+ 6 2.50000- 2163033103 155 3.50000+ 6 2.00000- 2 4.50000+ 6 2.00000- 2 5.50000+ 6 1.00000- 2163033103 156 6.00000+ 6 1.20000- 2 8.00000+ 6 1.20000- 2 9.00000+ 6 1.20000- 2163033103 157 1.10000+ 7 2.20000- 2 1.25000+ 7 1.00000- 2 1.40000+ 7 1.00000- 2163033103 158 1.70000+ 7 1.00000- 2 2.00000+ 7 0.00000+ 0 163033103 159 163033 0 160 1630 0 0 161 0 0 0 162 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0