ENTRY 10547 20181102 14441054700000001 SUBENT 10547001 20181102 14441054700100001 BIB 11 29 1054700100002 INSTITUTE (1USALRL) 1054700100003 REFERENCE (J,NSE,60,383,1976) 1054700100004 (J,NSE,64,892,1977) Renormalized data for 0.1-75 keV.1054700100005 (R,UCRL-77377,19751001) Preliminary data 1054700100006 AUTHOR (J.B.Czirr,G.S.Sidhu) 1054700100007 TITLE A Measurement of the Fission Cross Section of 235U 1054700100008 from 100 eV to 680 keV. 1054700100009 FACILITY (LINAC,1USALRL) 1054700100010 METHOD (TOF) Time-of-flight 1054700100011 DETECTOR (FISCH) Fission chambers 1054700100012 (GLASD) 6Li glass detectors for flux monitoring 1054700100013 CORRECTION Corrections were made for deadtime, absorption of 1054700100014 neutrons by fission chamber and li glass detector, and1054700100015 multiple reactions in li glass detector and fission 1054700100016 chamber. 1054700100017 ERR-ANALYS (ERR-S) Statistical error 1054700100018 (ERR-SYS) Systematic errors including flux monitor 1054700100019 efficiency, errors in deadtime corrections, error in 1054700100020 flux perturbation calculation, multiple scattering 1054700100021 correction errors in both Li glass detector and 1054700100022 fission chamber, self absorption in flux monitor and 1054700100023 fission chamber, normalization error, and errors in 1054700100024 energy dependence of the 6Li(n,alpha) reaction. 1054700100025 STATUS (TABLE) Table III, Nucl.Sci.Eng.60,383(1976) 1054700100026 HISTORY (19751014C) 1054700100027 (19780106U)BIB update. Converted to REACTOR formalism. 1054700100028 (20040517A) Converted to new date formats, lower case. 1054700100029 Data heading updated. 1054700100030 (20181014U) OS. Minor correction in sub.2 1054700100031 ENDBIB 29 0 1054700100032 NOCOMMON 0 0 1054700100033 ENDSUBENT 32 0 1054700199999 SUBENT 10547002 20181102 14441054700200001 BIB 3 8 1054700200002 REACTION 1((92-U-235(N,F),,SIG)/(3-LI-6(N,T)2-HE-4,,SIG)) 1054700200003 2(92-U-235(N,F),,SIG) 1054700200004 MONITOR 2(3-LI-6(N,T)2-HE-4,,SIG) 1054700200005 ((MONIT)92-U-235(N,F),,SIG) Normalized to thermal- 1054700200006 neutron cross section from ENDF/B-IV using data taken 1054700200007 in a separate measurement in the range 0.02 - 2000 eV.1054700200008 HISTORY (19780106A) Data replaced with published values 1054700200009 (20181014U) STATUS keyword deleted 1054700200010 ENDBIB 8 0 1054700200011 COMMON 2 3 1054700200012 EN-NRM 2MONIT 2 1054700200013 EV B 1054700200014 0.0253 585.4 1054700200015 ENDCOMMON 3 0 1054700200016 DATA 6 40 1054700200017 EN-MIN EN-MAX DATA 1DATA 2ERR-S ERR-SYS 1054700200018 KEV KEV NO-DIM B PER-CENT PER-CENT 1054700200019 0.10 0.20 1.667 20.2 0.6 1.3 1054700200020 0.20 0.30 2.052 19.3 0.6 1.3 1054700200021 0.30 0.40 1.578 12.5 0.9 1.3 1054700200022 0.40 0.50 1.851 12.9 0.9 1.3 1054700200023 0.50 0.60 2.250 14.2 0.8 1.3 1054700200024 0.60 0.80 1.881 10.5 0.7 1.3 1054700200025 0.80 1.0 1.500 7.40 0.9 1.3 1054700200026 1.0 1.5 1.810 7.01 0.7 1.3 1054700200027 1.5 2.0 1.736 6.13 0.9 1.3 1054700200028 2.0 2.25 1.580 5.07 1.6 1.3 1054700200029 3.5 4.5 1.823 4.27 1.2 1.3 1054700200030 4.5 5.5 1.731 3.63 1.1 1.3 1054700200031 6.1 6.5 1.611 3.01 1.7 1.3 1054700200032 6.5 7.5 1.758 3.11 1.2 1.3 1054700200033 7.5 8.5 1.631 2.70 1.3 1.3 1054700200034 8.5 10.0 1.849 2.84 1.0 1.3 1054700200035 10. 15. 1.852 2.47 0.6 1.4 1054700200036 15. 20. 1.941 2.21 0.7 1.5 1054700200037 20. 25. 2.031 2.065 0.8 1.6 1054700200038 25. 30. 2.108 1.967 0.9 1.7 1054700200039 40. 50. 2.253 1.73 1.2 1.8 1054700200040 50. 60. 2.375 1.71 1.0 2.0 1054700200041 60. 70. 2.467 1.706 0.8 2.3 1054700200042 70. 75. 2.399 1.625 1.3 2.5 1054700200043 80. 90. 2.20 1.48 2.5 2.1 1054700200044 165. 195. 0.913 1.31 7.0 2.0 1054700200045 210. 230. 0.421 1.24 4.1 2.0 1054700200046 230. 250. 0.360 1.235 3.3 2.0 1054700200047 250. 270. 0.416 1.23 2.9 2.0 1054700200048 275. 285. 0.556 1.21 5.3 2.0 1054700200049 295. 315. 0.802 1.17 3.3 2.0 1054700200050 315. 335. 1.06 1.18 2.7 2.0 1054700200051 335. 355. 1.29 1.15 2.2 2.0 1054700200052 355. 370. 1.53 1.16 2.1 2.0 1054700200053 400. 450. 2.15 1.10 3.1 2.0 1054700200054 450. 500. 2.52 1.06 2.3 2.0 1054700200055 500. 550. 2.93 1.075 2.2 2.0 1054700200056 550. 580. 3.18 1.08 2.9 2.0 1054700200057 600. 650. 3.38 1.04 2.2 2.0 1054700200058 650. 680. 3.46 1.02 2.2 2.0 1054700200059 ENDDATA 42 0 1054700200060 ENDSUBENT 59 0 1054700299999 ENDENTRY 2 0 1054799999999