Fe-56 dosimetry 531 0 0 0 2.60560+ 4 5.54540+ 1 0 0 0 16431 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 06431 1451 2 0.00000+ 0 0.00000+ 0 0 0 37 46431 1451 3 26-fe- 56 ornl eval-jul78 c.y.fu 6431 1451 4 dist-aug79 790612 6431 1451 5 experimental data available since the evaluation of fe-56 6431 1451 6 (n,p) cross sections by dudey and kennerley(1) were reviewed. 6431 1451 7 smith and meadows(2) reported new data from 4 to 10 mev, an energy6431 1451 8 range most important for application of this reaction to fission 6431 1451 9 reactor dosimetry. vonach(3) has recently called for attention 6431 1451 10 to his data(4) from 13 to 15 mev. further checks(3) resulted 6431 1451 11 in a reduction of the data errors from 4% to 2.5%. the data had 6431 1451 12 not been used in the dudey and kennerley evaluation but are 6431 1451 13 2 to 3% lower than the evaluated values. three single-energy 6431 1451 14 measurements(5-7) near 14.6 mev have been reported. the one 6431 1451 15 by dyer(5) is 1% higher than the endf/b-iv value, robertson 7% 6431 1451 16 higher, and qaim 4% lower. 6431 1451 17 inclusion of the new data in a subjective analysis results 6431 1451 18 in up to 10% reduction from the endf/b-iv values from threshold to6431 1451 19 6 mev, 2-3% reduction form 6 to 10 mev, and 1-2% reduction from 6431 1451 20 13-15 mev. the data of smith and meadows are relative to endf/b-46431 1451 21 u-238(n,f) cross sections and had been renormalized to endf/b-v 6431 1451 22 values before being used in the present evaluation. the effect 6431 1451 23 on the calculated fission spectrum average is estimated to be 6431 1451 24 a reduction of about 3% from endf/b-iv value. 6431 1451 25 references: 6431 1451 26 1. n. d. dudey and r. kennerley, "evaluation of fe-56(n,p)mn-56 6431 1451 27 cross sections for endf/b-iii," in endf/b-iv dosimetry file, 6431 1451 28 edited by b. a. magurno, bnl-ncs-50446(1975). 6431 1451 29 2. d. l. smith and j. w. meadows, nucl. sci. eng. 58,314(1975). 6431 1451 30 3. h. vonach,"status of some activation cross sections for 6431 1451 31 reactor neutron dosimetry in the range 13-15 mev," p. 361, 6431 1451 32 iaea-208(1975). 6431 1451 33 4. h. vonach et al., conf. nucl. cross sections and tech., 6431 1451 34 washington, nbs-sp-299, vol. 1, p. 885(1968). 6431 1451 35 5. n. c. dyer and j. h. hamilton, j. inorg. nucl. chem. 34, 1119 6431 1451 36 (1972). 6431 1451 37 6. j. c. robertson et al., j. nucl. en. 27, 139(1972). 6431 1451 38 7. s. m. qaim et al., conf. on chem. nucl. data, canterbury, 6431 1451 39 p. 121(1971). 6431 1451 40 1 451 44 16431 1451 41 2 151 4 16431 1451 42 3 103 19 16431 1451 43 33 103 32 16431 1451 44 0.00000+ 0 0.00000+ 0 0 0 0 06431 1 0 45 0.00000+ 0 0.00000+ 0 0 0 0 06431 0 0 46 2.60560+ 4 5.54540+ 1 0 0 1 06431 2151 47 2.60560+ 4 1.00000+ 0 0 0 1 06431 2151 48 1.00000- 5 2.00000+ 7 0 0 0 06431 2151 49 0.00000+ 0 5.00000- 1 0 0 0 06431 2151 50 0.00000+ 0 0.00000+ 0 0 0 0 06431 2 0 51 0.00000+ 0 0.00000+ 0 0 0 0 06431 0 0 52 2.60560+ 4 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