ENTRY 22194 20230517 231722194 0 1 SUBENT 22194001 20230517 231722194 1 1 BIB 12 32 22194 1 2 TITLE Measurements of eta of 235-U for subthermal neutron 22194 1 3 energies 22194 1 4 AUTHOR (H.Weigmann,B.Keck,J.A.Wartena,P.Geltenbort, 22194 1 5 K.Schreckenbach) 22194 1 6 REFERENCE (C,90MARSEI,3,(PI),33,1990) 22194 1 7 INSTITUTE (2ZZZGEL) H.W., B.K., J.A.W 22194 1 8 (2FR ILL) P.G., K.S. 22194 1 9 COMMENT Data have been normalised to 2.075 at 25 milli-eV. 22194 1 10 SAMPLE 'Black' metallic U sample of 4.59 g/cm2 inserted in 22194 1 11 cylindrical 6-Li sleeve to shield from out-of-time 22194 1 12 scattered neutrons. 22194 1 13 DETECTOR (SCIN) 5 cm diam and 5 cm thick NE213 liquid scinti- 22194 1 14 llator for detection of fission neutrons from sample. 22194 1 15 METHOD (PSD) To distinguish fission neutrons from gammas 22194 1 16 CORRECTION *Count losses of all kinds, especially due to analyzer 22194 1 17 and PSD dead-times 22194 1 18 *Backgrounds 22194 1 19 *Incomplete absorption and scattering of incident slow 22194 1 20 neutrons in the U and B sample 22194 1 21 *Multiple scattering of the fission neutrons produced 22194 1 22 in the U sample 22194 1 23 *Self-absorption of the gammas in the B sample 22194 1 24 ERR-ANALYS (ERR-S) Statistical error 22194 1 25 (ERR-1) Total systematic error. The data have been 22194 1 26 normalized to 2.075 at 25 milli-eV, therefore ERR-1 22194 1 27 goes to zero at this energy. 22194 1 28 In the figures of the main reference the error bars 22194 1 29 represent a linear addition of ERR-S and ERR-1. 22194 1 30 STATUS (TABLE) Data obtained from author on tape. 22194 1 31 HISTORY (19910719C) S.W. 22194 1 32 (20230517A) SD:Updated to new date formats,lower case. 22194 1 33 Corrections in all Subents. 22194 1 34 ENDBIB 32 0 22194 1 35 NOCOMMON 0 0 22194 1 36 ENDSUBENT 35 0 22194 199999 SUBENT 22194002 20230517 231722194 2 1 BIB 9 24 22194 2 2 REACTION (92-U-235(N,ABS),,ETA) 22194 2 3 FACILITY (LINAC,2ZZZGEL) Electron linac, 40 Hz repetition rate 22194 2 4 METHOD (TOF) 8.8 m flight path 22194 2 5 MONITOR (5-B-10(N,A)3-LI-7,PAR,SIG,G) 22194 2 6 INC-SOURCE (PHOTO) With liquid methane moderator as white source 22194 2 7 of subthermal neutrons. The beam was defined by a 22194 2 8 3.5 m collimation system also containing a 2 cm thick 22194 2 9 Be filter to reduce flux above 6.8 milli-eV. 22194 2 10 SAMPLE 0.11 g/cm2 thick 10-B slab replaced the U sample for 22194 2 11 the precise flux measurement, inserted in 6-Li sleeve.22194 2 12 DETECTOR (PROPC) Two parallel plate proportional counters used 22194 2 13 as flux monitors and located 80 cm upstream from the 22194 2 14 U sample. The first counter was as follows: 22194 2 15 1st run: 162 ug/cm2 6-LiF layer (95.65% 6-Li) 22194 2 16 evaporated on 40 micron thick Al backing 22194 2 17 2nd run: 3.6 ug/cm2 10-B layer (90% 10-B) 22194 2 18 evaporated on 40 micron thick Al backing 22194 2 19 and the second counter: 22194 2 20 both runs: 279 ug/cm2 uf4 (97.6% 235-U) evaporated 22194 2 21 on Au coated 3.5 micron mylar foil. 22194 2 22 (SCIN) Gammas from the boron sample were detected 22194 2 23 with a hydrogen free C6F6 liquid scintillator. 22194 2 24 STATUS (TABLE) Data obtained from author on tape. 22194 2 25 HISTORY (20230517A) SD: Data units corrected. 22194 2 26 ENDBIB 24 0 22194 2 27 NOCOMMON 0 0 22194 2 28 DATA 4 73 22194 2 29 EN DATA ERR-S ERR-1 22194 2 30 MILLI-EV PRT/REAC PRT/REAC PRT/REAC 22194 2 31 1.80 2.018 0.015 0.131 22194 2 32 2.25 2.026 0.010 0.066 22194 2 33 2.75 2.024 0.007 0.033 22194 2 34 3.50 2.036 0.005 0.017 22194 2 35 4.50 2.045 0.004 0.009 22194 2 36 5.50 2.050 0.005 0.008 22194 2 37 6.50 2.052 0.006 0.007 22194 2 38 7.50 2.054 0.006 0.006 22194 2 39 8.50 2.062 0.006 0.005 22194 2 40 9.50 2.052 0.005 0.004 22194 2 41 11.00 2.059 0.004 0.003 22194 2 42 13.00 2.064 0.004 0.002 22194 2 43 15.00 2.071 0.003 0.002 22194 2 44 17.00 2.068 0.004 0.001 22194 2 45 19.00 2.071 0.004 0.001 22194 2 46 21.00 2.082 0.005 0.001 22194 2 47 23.00 2.066 0.005 0.000 22194 2 48 25.00 2.075 0.005 0.000 22194 2 49 27.00 2.071 0.006 0.000 22194 2 50 29.00 2.078 0.006 0.001 22194 2 51 31.00 2.080 0.006 0.001 22194 2 52 33.00 2.084 0.007 0.001 22194 2 53 35.00 2.080 0.007 0.001 22194 2 54 37.00 2.073 0.008 0.002 22194 2 55 39.00 2.089 0.011 0.002 22194 2 56 42.50 2.072 0.011 0.002 22194 2 57 47.50 2.092 0.012 0.003 22194 2 58 52.50 2.087 0.007 0.006 22194 2 59 57.50 2.092 0.008 0.012 22194 2 60 62.50 2.082 0.007 0.013 22194 2 61 67.50 2.089 0.008 0.013 22194 2 62 72.50 2.085 0.009 0.015 22194 2 63 77.50 2.082 0.009 0.016 22194 2 64 82.50 2.080 0.010 0.016 22194 2 65 87.50 2.074 0.010 0.017 22194 2 66 92.50 2.073 0.011 0.017 22194 2 67 97.50 2.086 0.011 0.017 22194 2 68 105.00 2.065 0.008 0.016 22194 2 69 115.00 2.063 0.009 0.016 22194 2 70 125.00 2.057 0.009 0.016 22194 2 71 135.00 2.058 0.009 0.016 22194 2 72 145.00 2.050 0.010 0.016 22194 2 73 155.00 2.044 0.010 0.016 22194 2 74 165.00 2.035 0.011 0.016 22194 2 75 175.00 2.027 0.011 0.016 22194 2 76 185.00 2.021 0.011 0.016 22194 2 77 195.00 2.016 0.011 0.016 22194 2 78 205.00 2.000 0.012 0.016 22194 2 79 215.00 1.989 0.012 0.016 22194 2 80 225.00 1.995 0.012 0.016 22194 2 81 235.00 1.975 0.013 0.016 22194 2 82 245.00 1.966 0.013 0.016 22194 2 83 255.00 1.969 0.013 0.016 22194 2 84 265.00 1.962 0.014 0.016 22194 2 85 275.00 1.956 0.014 0.016 22194 2 86 285.00 1.967 0.014 0.016 22194 2 87 295.00 1.985 0.014 0.016 22194 2 88 305.00 1.997 0.015 0.016 22194 2 89 315.00 2.031 0.016 0.016 22194 2 90 325.00 2.046 0.016 0.016 22194 2 91 335.00 2.074 0.017 0.017 22194 2 92 345.00 2.087 0.017 0.017 22194 2 93 355.00 2.110 0.018 0.017 22194 2 94 365.00 2.115 0.018 0.017 22194 2 95 375.00 2.132 0.019 0.017 22194 2 96 385.00 2.139 0.019 0.018 22194 2 97 395.00 2.146 0.020 0.018 22194 2 98 405.00 2.159 0.020 0.018 22194 2 99 415.00 2.160 0.021 0.018 22194 2 100 425.00 2.138 0.020 0.018 22194 2 101 435.00 2.146 0.022 0.018 22194 2 102 445.00 2.130 0.022 0.018 22194 2 103 455.00 2.135 0.022 0.018 22194 2 104 ENDDATA 75 0 22194 2 105 ENDSUBENT 104 0 22194 299999 SUBENT 22194003 20230517 231722194 3 1 BIB 8 19 22194 3 2 REACTION (92-U-235(N,ABS),,ETA) 22194 3 3 FACILITY (REAC,2FR ILL) High flux reactor 22194 3 4 MONITOR (48-CD-0(N,G),,SIG) 22194 3 5 INC-SOURCE (REAC) Thermal neutron guide with double chopper 22194 3 6 set-up. The two choppers were separated by 2.9 m, and 22194 3 7 were run at slightly different speeds such that their 22194 3 8 relative phase and therefore en is varied continuously22194 3 9 SAMPLE 0.7 mm thick Cd 'black' capture sample replaced the 22194 3 10 U sample for the precise flux measurement, inserted in22194 3 11 6-Li sleeve. 22194 3 12 DETECTOR (IOCH) Used as flux monitor, loaded with a 22194 3 13 175 ug/cm2 235-U sample (99% 235-U) deposited 22194 3 14 onto Au coated 3.5 micron mylar foil, and located 22194 3 15 65 cm upstream from the U sample. 22194 3 16 (COIN,SCIN,SCIN) Two hydrogen free C6F6 liquid 22194 3 17 scintillators to detect gammas from the Cd capture 22194 3 18 sample. 22194 3 19 STATUS (TABLE) Data obtained from author on tape. 22194 3 20 HISTORY (20230517A) SD: Data units corrected. 22194 3 21 ENDBIB 19 0 22194 3 22 NOCOMMON 0 0 22194 3 23 DATA 4 47 22194 3 24 EN DATA ERR-S ERR-1 22194 3 25 MILLI-EV PRT/REAC PRT/REAC PRT/REAC 22194 3 26 1.50 1.987 0.012 0.030 22194 3 27 1.80 2.024 0.012 0.025 22194 3 28 2.25 2.038 0.007 0.023 22194 3 29 2.75 2.042 0.003 0.021 22194 3 30 3.50 2.026 0.012 0.008 22194 3 31 4.50 2.031 0.012 0.007 22194 3 32 5.50 2.046 0.012 0.007 22194 3 33 6.50 2.056 0.011 0.006 22194 3 34 7.50 2.052 0.011 0.006 22194 3 35 8.50 2.070 0.009 0.006 22194 3 36 9.50 2.046 0.010 0.005 22194 3 37 11.00 2.056 0.006 0.005 22194 3 38 13.00 2.070 0.007 0.004 22194 3 39 15.00 2.057 0.006 0.003 22194 3 40 17.00 2.063 0.006 0.003 22194 3 41 19.00 2.082 0.007 0.002 22194 3 42 21.00 2.077 0.006 0.001 22194 3 43 23.00 2.083 0.008 0.000 22194 3 44 25.00 2.075 0.007 0.000 22194 3 45 27.00 2.068 0.007 0.001 22194 3 46 29.00 2.071 0.007 0.001 22194 3 47 31.00 2.082 0.009 0.002 22194 3 48 33.00 2.087 0.007 0.002 22194 3 49 35.00 2.072 0.009 0.002 22194 3 50 36.76 2.079 0.009 0.003 22194 3 51 38.50 2.077 0.009 0.003 22194 3 52 40.36 2.075 0.009 0.003 22194 3 53 42.35 2.103 0.009 0.004 22194 3 54 44.51 2.089 0.010 0.004 22194 3 55 46.82 2.108 0.010 0.004 22194 3 56 49.33 2.081 0.010 0.004 22194 3 57 52.04 2.088 0.011 0.004 22194 3 58 54.98 2.073 0.011 0.004 22194 3 59 58.18 2.093 0.011 0.004 22194 3 60 61.66 2.091 0.011 0.004 22194 3 61 65.47 2.099 0.011 0.004 22194 3 62 69.64 2.089 0.011 0.004 22194 3 63 74.23 2.103 0.011 0.005 22194 3 64 79.27 2.094 0.012 0.005 22194 3 65 84.86 2.094 0.012 0.005 22194 3 66 91.06 2.078 0.011 0.006 22194 3 67 97.96 2.089 0.011 0.006 22194 3 68 105.67 2.073 0.012 0.006 22194 3 69 114.34 2.070 0.011 0.008 22194 3 70 124.11 2.068 0.013 0.011 22194 3 71 135.20 2.067 0.015 0.018 22194 3 72 147.83 2.042 0.018 0.029 22194 3 73 ENDDATA 49 0 22194 3 74 ENDSUBENT 73 0 22194 399999 ENDENTRY 3 0 2219499999999