IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.906500+4 6.492800+1 0 0 0 16436 1451 1 0.000000+0 0.000000+0 0 0 0 06436 1451 2 0.000000+0 0.000000+0 0 0 35 46436 1451 3 29-Cu- 65 ORNL EVAL-JUL78 C.Y.FU 6436 1451 4 DIST-MAR84 790612 6436 1451 5 THE EVALUATION OF CU-65(N,2N) CROSS SECTIONS BY ROSE(1) FOR 6436 1451 6 ENDF/B-IV WAS BASED ON 3 MEASUREMENTS(2-4). THESE WERE EXAMINED 6436 1451 7 TOGETHER WITH MORE RECENT DATA(5-9). ALL EXCEPT ONE HAVE ERROR 6436 1451 8 BARS THAT ARE WITHIN 2 PERCENT OF THE ENDF/B-IV EVALUATION. THE 6436 1451 9 EXCEPTION IS MANNHART AND VONACH(5), WHOSE DATA ARE 10 PERCENT 6436 1451 10 LOWER THAN ENDF/B-IV BUT HAVE ERRORS AS SMALL AS 1.6 PERCENT. IN 6436 1451 11 LOOKING AT THIS MEASUREMENT MORE CLOSELY(10,11), WE FOUND THAT 6436 1451 12 THE DATA WERE ELABORIOUSLY TAKEN AND ARE AMOUNG THE MOST 6436 1451 13 TRUSTWORTHY. THEREFORE, THE DATA OF MANNHART AND VONACH MUST BE 6436 1451 14 INCLUDED IN A NEW EVALUATION. HOWEVER, THE WEIGHT GIVEN TO THEIR 6436 1451 15 DATA IS SOMEWHAT ARBITRARY. 6436 1451 16 THE NEW EVALUATION HAS VALUES AT MOST 5 PERCENT SMALLER THAN 6436 1451 17 ENDF/B-IV IN THE ENERGY RANGE 12 TO 18 MEV. AN ERROR BAND OF 6436 1451 18 5 PERCENT PLUS 15 MB WOULD ENCLOSE 70 PERCENT OF ALL AVAILABLE 6436 1451 19 DATA IN CSISRS(MAY 1978) AND 90 PERCENT OF THE DATA IN REFS. 2-9. 6436 1451 20 REFERENCES: 6436 1451 21 1. P. F. ROSE,"THE CU-65(N,2N)CU-64 REACTION FOR ENDF/B-IV," 6436 1451 22 IN ENDF/B-IV DOSIMETRY FILE, EDITED BY B. A. MAGURNO, 6436 1451 23 BNL-NCS-50446(1975). 6436 1451 24 2. R. J. PRESTWOOD AND B. P. BAYHURST, PHYS. REV. 121,1438(1961).6436 1451 25 3. A. PAULSEN AND H. LISKIEN, NUCLEONIK 7, 117(1965). 6436 1451 26 4. D. C. SANTRY AND J. P. BUTLER, CAN. J. PHYS. 44, 1183(1964). 6436 1451 27 5. W. MANNHART AND H. VONACH, Z. PHYS. A272, 279(1975). 6436 1451 28 6. R. MOGHARRAB AND H. NEUERT, ATOMKERNENERGIE 19, 107(1972). 6436 1451 29 7. S. M. QAIM, NUCL. PHYS. A185, 614(1972). 6436 1451 30 8. J. C. ROBERTSON ET AL., J. NUCL. EN. 27, 139(1973). 6436 1451 31 9. J. ARAMINOWICZ AND J. DRESLER, U. OF LODZ(POLLAND) REPORT 6436 1451 32 INR-1464, P. 14(1973). 6436 1451 33 10. H. VONACH, "STATUS OF SOME ACTIVATION CROSS SECTIONS FOR 6436 1451 34 REACTOR NEUTRON DOSIMETRY IN THE RANGE 13-15 MEV,"IAEA-208, 6436 1451 35 P. 361(1975). 6436 1451 36 11. H. VONACH ET AL., PROC. CONF. ON NUCLEAR CROSS SECTIONS AND 6436 1451 37 TECHNOLOGY, NBS-SP 299, VOL. 1, P. 885(1968). 6436 1451 38 1 451 42 16436 1451 39 2 151 4 16436 1451 40 3 16 11 16436 1451 41 33 16 29 16436 1451 42 0.000000+0 0.000000+0 0 0 0 06436 1 0 43 0.000000+0 0.000000+0 0 0 0 06436 0 0 44 2.906500+4 6.492800+1 0 0 1 06436 2151 45 2.906500+4 1.000000+0 0 0 1 06436 2151 46 1.000000-5 2.000000+7 0 0 0 06436 2151 47 1.500000+0 7.302000-1 0 0 0 06436 2151 48 0.000000+0 0.000000+0 0 0 0 06436 2 0 49 0.000000+0 0.000000+0 0 0 0 06436 0 0 50 2.906500+4 6.492800+1 0 99 0 06436 3 16 51 0.000000+0-9.910000+6 0 0 1 236436 3 16 52 23 2 6436 3 16 53 1.006300+7 0.000000+0 1.050000+7 3.458000-2 1.100000+7 1.544000-16436 3 16 54 1.150000+7 3.134000-1 1.200000+7 4.754000-1 1.250000+7 6.000000-16436 3 16 55 1.300000+7 6.980000-1 1.350000+7 7.830000-1 1.400000+7 8.530000-16436 3 16 56 1.450000+7 9.080000-1 1.500000+7 9.530000-1 1.550000+7 9.910000-16436 3 16 57 1.600000+7 1.023000+0 1.650000+7 1.047000+0 1.700000+7 1.064000+06436 3 16 58 1.750000+7 1.081000+0 1.800000+7 1.095000+0 1.850000+7 1.105000+06436 3 16 59 1.900000+7 1.109000+0 1.920000+7 1.103000+0 1.940000+7 1.085000+06436 3 16 60 1.960000+7 1.056000+0 2.000000+7 9.796000-1 6436 3 16 61 0.000000+0 0.000000+0 0 0 0 06436 3 0 62 0.000000+0 0.000000+0 0 0 0 06436 0 0 63 2.906500+4 6.492800+1 0 0 0 1643633 16 64 0.000000+0 0.000000+0 0 16 0 1643633 16 65 0.000000+0 0.000000+0 1 5 153 17643633 16 66 1.000000-5 1.006000+7 1.050000+7 1.100000+7 1.150000+7 1.200000+7643633 16 67 1.250000+7 1.300000+7 1.350000+7 1.450000+7 1.550000+7 1.650000+7643633 16 68 1.750000+7 1.850000+7 1.920000+7 1.960000+7 2.000000+7 0.000000+0643633 16 69 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0643633 16 70 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0643633 16 71 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0643633 16 72 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0643633 16 73 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0643633 16 74 1.936000-1 2.710400-2 1.552320-2 1.197500-2 9.879410-3 8.729800-3643633 16 75 8.139730-3 7.732700-3 7.207500-3 6.847100-3 6.504770-3 5.854300-3643633 16 76 5.268870-3 4.215100-3 1.210000-2 5.544000-3 4.276800-3 3.528400-3643633 16 77 3.117790-3 2.907000-3 2.761700-3 2.574100-3 2.445400-3 2.323100-3643633 16 78 2.090820-3 1.881700-3 1.505390-3 4.900000-3 3.402000-3 2.806700-3643633 16 79 2.480060-3 2.312400-3 2.196800-3 2.047600-3 1.945210-3 1.847900-3643633 16 80 1.663150-3 1.496800-3 1.197470-3 3.600000-3 2.673000-3 2.362000-3643633 16 81 2.202310-3 2.092200-3 1.950080-3 1.852600-3 1.759950-3 1.584000-3643633 16 82 1.425560-3 1.140400-3 3.025000-3 2.405700-3 2.243090-3 2.130900-3643633 16 83 1.986190-3 1.886900-3 1.792540-3 1.613300-3 1.451960-3 1.161600-3643633 16 84 2.916000-3 2.447000-3 2.324660-3 2.166800-3 2.058420-3 1.955500-3643633 16 85 1.759950-3 1.584000-3 1.267160-3 2.809000-3 2.535120-3 2.362900-3643633 16 86 2.244780-3 2.132500-3 1.919290-3 1.727400-3 1.381890-3 2.809000-3643633 16 87 2.487290-3 2.362900-3 2.244780-3 2.020300-3 1.818270-3 1.454600-3643633 16 88 2.704000-3 2.440400-3 2.318340-3 2.086500-3 1.877860-3 1.502300-3643633 16 89 2.704000-3 2.440400-3 2.196320-3 1.976700-3 1.581350-3 2.704000-3643633 16 90 2.311920-3 2.080700-3 1.664580-3 2.704000-3 2.190240-3 1.752200-3643633 16 91 2.704000-3 1.946900-3 2.704000-3 643633 16 92 0.000000+0 0.000000+0 0 0 0 0643633 0 93 0.000000+0 0.000000+0 0 0 0 06436 0 0 94 0.000000+0 0.000000+0 0 0 0 0 0 0 0 95 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0