IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.605600+4 5.545400+1 0 0 0 17266 1451 1 0.000000+0 0.000000+0 0 0 0 07266 1451 2 0.000000+0 0.000000+0 0 0 48 87266 1451 3 26-Fe- 56 ORNL EVAL-JUL78 C.Y.FU 7266 1451 4 DIST-MAR84 840809 7266 1451 5 FE-56(N,2N) 7266 1451 6 FE-56 (N,2N) CROSS SECTIONS WERE BASED ON FREHAUT AND 7266 1451 7 MOSINSKI(1) FROM 12 TO 15 MEV AND TWO OTHER VALUES NEAR 14 MEV 7266 1451 8 QUOTED IN BN.-325(2). EXTRAPOLATION TO 20 MEV WAS BASED ON OUR 7266 1451 9 MODEL CALCULATION(3). 7266 1451 10 1. J. FREHAUT AND G. MOSINSKI, CONF. ON NUCLEAR CROSS SECTIONS 7266 1451 11 AND TECHNOLOGY, WASHINGTON, MAR. 3-7, 1975 (NBS-SP-425). 7266 1451 12 2. D. I. GARBER AND R. R. KINSEY, BNL-325, THIRD EDITION(1976). 7266 1451 13 3. C. Y. FU., PROC. CONF. ON NUCLEAR CROSS SECTIONS FOR 7266 1451 14 TECHNOLOGY, KNOXVILLE, OCT. 22-26, 1979. 7266 1451 15 FE-56(N,P) 7266 1451 16 EXPERIMENTAL DATA AVAILABLE SINCE THE EVALUATION OF FE-56 7266 1451 17 (N,P) CROSS SECTIONS BY DUDEY AND KENNERLEY(1) WERE REVIEWED. 7266 1451 18 SMITH AND MEADOWS(2) REPORTED NEW DATA FROM 4 TO 10 MEV, AN ENERGY7266 1451 19 RANGE MOST IMPORTANT FOR APPLICATION OF THIS REACTION TO FISSION 7266 1451 20 REACTOR DOSIMETRY. VONACH(3) HAS RECENTLY CALLED FOR ATTENTION 7266 1451 21 TO HIS DATA(4) FROM 13 TO 15 MEV. FURTHER CHECKS(3) RESULTED 7266 1451 22 IN A REDUCTION OF THE DATA ERRORS FROM 4 TO 2.5 . THE DATA HAD 7266 1451 23 NOT BEEN USED IN THE DUDEY AND KENNERLEY EVALUATION BUT ARE 7266 1451 24 2 TO 3 LOWER THAN THE EVALUATED VALUES. THREE SINGLE-ENERGY 7266 1451 25 MEASUREMENTS(5-7) NEAR 14.6 MEV HAVE BEEN REPORTED. THE ONE 7266 1451 26 BY DYER(5) IS 1 HIGHER THAN THE ENDF/B-IV VALUE, ROBERTSON 7 7266 1451 27 HIGHER, AND QAIM 4 LOWER. 7266 1451 28 INCLUSION OF THE NEW DATA IN A SUBJECTIVE ANALYSIS RESULTS 7266 1451 29 IN UP TO 10 REDUCTION FROM THE ENDF/B-IV VALUES FROM THRESHOLD TO7266 1451 30 6 MEV, 2-3 REDUCTION FORM 6 TO 10 MEV, AND 1-2 REDUCTION FROM 7266 1451 31 13-15 MEV. THE DATA OF SMITH AND MEADOWS ARE RELATIVE TO ENDF/B-47266 1451 32 U-238(N,F) CROSS SECTIONS AND HAD BEEN RENORMALIZED TO ENDF/B-V 7266 1451 33 VALUES BEFORE BEING USED IN THE PRESENT EVALUATION. THE EFFECT 7266 1451 34 ON THE CALCULATED FISSION SPECTRUM AVERAGE IS ESTIMATED TO BE 7266 1451 35 A REDUCTION OF ABOUT 3 FROM ENDF/B-IV VALUE. 7266 1451 36 REFERENCES 7266 1451 37 1. N. D. DUDEY AND R. KENNERLEY, EVALUATION OF FE-56(N,P)MN-56 7266 1451 38 CROSS SECTIONS FOR ENDF/B-III, IN ENDF/B-IV DOSIMETRY FILE, 7266 1451 39 EDITED BY B. A. MAGURNO, BNL-NCS-50446(1975). 7266 1451 40 2. D. L. SMITH AND J. W. MEADOWS, NUCL. SCI. ENG. 58,314(1975). 7266 1451 41 3. H. VONACH, STATUS OF SOME ACTIVATION CROSS SECTIONS FOR 7266 1451 42 REACTOR NEUTRON DOSIMETRY IN THE RANGE 13-15 MEV, P. 361, 7266 1451 43 IAEA-208(1975). 7266 1451 44 4. H. VONACH ET AL., CONF. NUCL. CROSS SECTIONS AND TECH., 7266 1451 45 WASHINGTON, NBS-SP-299, VOL. 1, P. 885(1968). 7266 1451 46 5. N. C. DYER AND J. H. HAMILTON, J. INORG. NUCL. CHEM. 34, 1119 7266 1451 47 (1972). 7266 1451 48 6. J. C. ROBERTSON ET AL., J. NUCL. EN. 27, 139(1972). 7266 1451 49 7. S. M. QAIM ET AL., CONF. ON CHEM. NUCL. DATA, CANTERBURY, 7266 1451 50 P. 121(1971). 7266 1451 51 1 451 59 17266 1451 52 2 151 4 17266 1451 53 3 16 10 17266 1451 54 3 103 19 17266 1451 55 8 16 3 17266 1451 56 8 103 6 17266 1451 57 9 16 4 17266 1451 58 9 103 4 17266 1451 59 0.000000+0 0.000000+0 0 0 0 07266 1 0 60 0.000000+0 0.000000+0 0 0 0 07266 0 0 61 2.605600+4 5.545400+1 0 0 1 07266 2151 62 2.605600+4 1.000000+0 0 0 1 07266 2151 63 1.000000-5 2.000000+7 0 0 0 07266 2151 64 0.000000+0 5.000000-1 0 0 0 07266 2151 65 0.000000+0 0.000000+0 0 0 0 07266 2 0 66 0.000000+0 0.000000+0 0 0 0 07266 0 0 67 2.605600+4 5.545400+1 0 99 0 07266 3 16 68 0.000000+0-1.120400+7 0 0 2 207266 3 16 69 2 2 20 4 7266 3 16 70 1.140600+7 0.000000+0 1.160000+7 1.400000-2 1.180000+7 3.100000-27266 3 16 71 1.200000+7 5.000000-2 1.230000+7 9.600000-2 1.260000+7 1.700000-17266 3 16 72 1.300000+7 2.530000-1 1.350000+7 3.570000-1 1.400000+7 4.650000-17266 3 16 73 1.450000+7 5.100000-1 1.500000+7 5.680000-1 1.530000+7 5.950000-17266 3 16 74 1.560000+7 6.160000-1 1.600000+7 6.330000-1 1.650000+7 6.430000-17266 3 16 75 1.700000+7 6.450000-1 1.740000+7 6.430000-1 1.800000+7 6.360000-17266 3 16 76 1.900000+7 6.190000-1 2.000000+7 5.970000-1 7266 3 16 77 0.000000+0 0.000000+0 0 0 0 07266 3 0 78 2.605600+4 5.545400+1 0 99 0 07266 3103 79 0.000000+0-2.913000+6 0 0 3 477266 3103 80 2 2 12 4 47 27266 3103 81 2.965500+6 0.000000+0 3.000000+6 7.000000-9 4.000000+6 6.000000-67266 3103 82 4.250000+6 3.200000-5 4.500000+6 1.400000-4 4.600000+6 2.400000-47266 3103 83 4.800000+6 5.650000-4 5.000000+6 1.100000-3 5.250000+6 2.500000-37266 3103 84 5.500000+6 4.700000-3 5.750000+6 8.000000-3 6.000000+6 1.250000-27266 3103 85 6.200000+6 1.590000-2 6.400000+6 1.920000-2 6.600000+6 2.240000-27266 3103 86 6.800000+6 2.560000-2 7.000000+6 2.870000-2 7.500000+6 3.610000-27266 3103 87 8.000000+6 4.270000-2 8.500000+6 4.890000-2 9.000000+6 5.500000-27266 3103 88 9.500000+6 6.140000-2 1.000000+7 6.930000-2 1.050000+7 7.750000-27266 3103 89 1.100000+7 8.700000-2 1.150000+7 9.560000-2 1.200000+7 1.030000-17266 3103 90 1.220000+7 1.060000-1 1.240000+7 1.080000-1 1.260000+7 1.100000-17266 3103 91 1.280000+7 1.110000-1 1.300000+7 1.120000-1 1.340000+7 1.125000-17266 3103 92 1.380000+7 1.114000-1 1.420000+7 1.088000-1 1.460000+7 1.050000-17266 3103 93 1.500000+7 9.940000-2 1.550000+7 9.070000-2 1.600000+7 8.180000-27266 3103 94 1.650000+7 7.620000-2 1.700000+7 6.920000-2 1.750000+7 6.350000-27266 3103 95 1.800000+7 5.890000-2 1.850000+7 5.470000-2 1.900000+7 5.130000-27266 3103 96 1.950000+7 4.920000-2 2.000000+7 4.880000-2 7266 3103 97 0.000000+0 0.000000+0 0 0 0 07266 3 0 98 0.000000+0 0.000000+0 0 0 0 07266 0 0 99 2.605600+4 5.545400+1 0 0 1 07266 8 16 100 2.605500+4 0.000000+0 9 0 6 72657266 8 16 101 8.520400+7 2.000000+0 2.505500+4 1.000000+0 2.314000+5 1.020000+07266 8 16 102 0.000000+0 0.000000+0 0 0 0 07266 8 0 103 2.605600+4 5.545400+1 0 0 1 07266 8103 104 2.505600+4 0.000000+0 9 0 24 72567266 8103 105 9.282600+3 1.000000+0 2.605600+4 1.160000-2 3.257000+5 1.060000+07266 8103 106 9.282600+3 1.000000+0 2.605600+4 1.460000-1 7.355000+5 1.040000+07266 8103 107 9.282600+3 1.000000+0 2.605600+4 2.790000-1 1.037900+6 1.030000+07266 8103 108 9.282600+3 1.000000+0 2.605600+4 5.630000-1 2.848600+6 1.010000+07266 8103 109 0.000000+0 0.000000+0 0 0 0 07266 8 0 110 0.000000+0 0.000000+0 0 0 0 07266 0 0 111 2.605600+4 5.545400+1 0 0 1 07266 9 16 112 0.000000+0-1.120400+7 0 0 1 27266 9 16 113 2 2 7266 9 16 114 1.140600+7 1.000000+0 2.000000+7 1.000000+0 7266 9 16 115 0.000000+0 0.000000+0 0 0 0 07266 9 0 116 2.605600+4 5.545400+1 0 0 1 07266 9103 117 0.000000+0-2.913000+6 0 0 1 27266 9103 118 2 2 7266 9103 119 2.965500+6 1.000000+0 2.000000+7 1.000000+0 7266 9103 120 0.000000+0 0.000000+0 0 0 0 07266 9 0 121 0.000000+0 0.000000+0 0 0 0 07266 0 0 122 0.000000+0 0.000000+0 0 0 0 0 0 0 0 123 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0