ENTRY 21197 20230516 231721197 0 1 SUBENT 21197001 20230516 231721197 1 1 BIB 11 31 21197 1 2 TITLE The energy dependence of the fission-neutron yield per 21197 1 3 neutron absorbed in U-233 over the range 0.025- 2.2 eV 21197 1 4 AUTHOR (J.E.Sanders,H.M.Skarsgard,C.J.Kenward) 21197 1 5 REFERENCE (J,JNE,5,186,1957) 21197 1 6 (R,AERE-NP/R-2076,7,1957) abst. 21197 1 7 INSTITUTE (2UK HAR) 21197 1 8 FACILITY (REAC,2UK HAR) BEPO reactor 21197 1 9 (SPECC,2UK HAR) K-Cl or Cu crystal. 21197 1 10 SAMPLE Metallic U-233 discs, isotopic purity 99.3%, 21197 1 11 2 inch in diameter and 3 to 5 mm thick. 21197 1 12 METHOD Detection of emitted fission neutrons. 21197 1 13 DETECTOR (BF3) 16 BF-3 counters embedded in paraffin wax 21197 1 14 arranged cylindrically round the sample. 21197 1 15 (PROPC) Proportional counter containing boron foils 21197 1 16 to monitor flux. 21197 1 17 CORRECTION Corrections made for- 21197 1 18 higher order reflections from the crystal, correction 21197 1 19 did not exceed 5%. 21197 1 20 Transmission of U-233 disc less than 2.1%. 21197 1 21 Scattering by U-233 disc causing neutron loss from 21197 1 22 the sample, less than 1.6%. 21197 1 23 Correction of less than 3.6% to allow for 21197 1 24 neutron absorption in Cu can containing the sample. 21197 1 25 Variation with energy of neutron absorption in B-10 21197 1 26 monitor counter, less than 0.9%. 21197 1 27 Fast fission multiplication in neutron disc, less 21197 1 28 than 1%. 21197 1 29 STATUS (NDD) From NEUDADA. 21197 1 30 HISTORY (19791128T) 21197 1 31 (20230516A) SD:Updated to new date formats,lower case. 21197 1 32 Corrections in all Subents. 21197 1 33 ENDBIB 31 0 21197 1 34 NOCOMMON 0 0 21197 1 35 ENDSUBENT 34 0 21197 199999 SUBENT 21197002 20230516 231721197 2 1 BIB 5 16 21197 2 2 REACTION ((94-PU-239(N,ABS),,ETA)//(94-PU-239(N,ABS),,ETA)) 21197 2 3 REL-REF (N,,J.A.Harvey+,B,PR.NUC.EN.,1,1,1956) Chapter I. 21197 2 4 (N,,H.Palevsky,C,55GENEVA,4,311,1955) 21197 2 5 The Harwell measurements have been normalized to the 21197 2 6 Brookhaven data (Palevsky) over the range 0.05-0.10 eV,21197 2 7 these in turn being referred to an average thermal eta 21197 2 8 value of 2.29 (J.A.Harvey, see REL-REF). 21197 2 9 ERR-ANALYS The errors indicated on fig.3 have been computed by 21197 2 10 combining the counting standard deviation with the 21197 2 11 estimation of the errors in each of the corrections 21197 2 12 applied (that for higher order reflection being the 21197 2 13 most important). 21197 2 14 STATUS Data given as 17 points for K-Cl neutrons and 13 points21197 2 15 for Cu neutrons in fig.3 of the J.Nucl.En.,5(1957)186 21197 2 16 HISTORY (20230516A) SD: Reaction code corrected and presented 21197 2 17 as reaction ratio. 21197 2 18 ENDBIB 16 0 21197 2 19 COMMON 1 3 21197 2 20 EN-DN 21197 2 21 EV 21197 2 22 0.0253 21197 2 23 ENDCOMMON 3 0 21197 2 24 DATA 2 27 21197 2 25 EN-NM DATA 21197 2 26 EV NO-DIM 21197 2 27 4.800E-02 2.315 21197 2 28 5.800E-02 2.278 21197 2 29 6.800E-02 2.285 21197 2 30 8.300E-02 2.285 21197 2 31 1.000E-01 2.255 21197 2 32 1.350E-01 2.235 21197 2 33 1.410E-01 2.250 21197 2 34 1.900E-01 2.250 21197 2 35 2.500E-01 2.283 21197 2 36 3.340E-01 2.250 21197 2 37 4.300E-01 2.280 21197 2 38 4.300E-01 2.320 21197 2 39 6.300E-01 2.268 21197 2 40 6.350E-01 2.305 21197 2 41 7.900E-01 2.250 21197 2 42 1.070E+00 2.293 21197 2 43 1.260E+00 2.250 21197 2 44 1.300E+00 2.222 21197 2 45 1.410E+00 2.157 21197 2 46 1.540E+00 2.157 21197 2 47 1.550E+00 2.067 21197 2 48 1.660E+00 2.006 21197 2 49 1.750E+00 2.066 21197 2 50 1.800E+00 1.934 21197 2 51 2.020E+00 2.065 21197 2 52 2.090E+00 1.840 21197 2 53 2.160E+00 1.873 21197 2 54 ENDDATA 29 0 21197 2 55 ENDSUBENT 54 0 21197 299999 SUBENT 21197003 20230516 231721197 3 1 BIB 3 3 21197 3 2 REACTION (92-U-233(N,ABS),,ALF) 21197 3 3 ASSUMED (ASSUM,92-U-233(N,F),,NU) 21197 3 4 HISTORY (20230516U) SD: STATUS updated. 21197 3 5 ENDBIB 3 0 21197 3 6 COMMON 1 3 21197 3 7 ASSUM 21197 3 8 NO-DIM 21197 3 9 2.504 21197 3 10 ENDCOMMON 3 0 21197 3 11 DATA 2 12 21197 3 12 EN DATA 21197 3 13 EV NO-DIM 21197 3 14 1.07E+00 9.20E-02 21197 3 15 1.26E+00 1.13E-01 21197 3 16 1.30E+00 1.27E-01 21197 3 17 1.41E+00 1.61E-01 21197 3 18 1.54E+00 1.61E-01 21197 3 19 1.55E+00 2.11E-01 21197 3 20 1.66E+00 2.48E-01 21197 3 21 1.75E+00 2.12E-01 21197 3 22 1.80E+00 2.95E-01 21197 3 23 2.02E+00 2.13E-01 21197 3 24 2.09E+00 3.61E-01 21197 3 25 2.16E+00 3.37E-01 21197 3 26 ENDDATA 14 0 21197 3 27 ENDSUBENT 26 0 21197 399999 ENDENTRY 3 0 2119799999999