ENTRY 12370 20220304 14981237000000001 SUBENT 12370001 20220304 14981237000100001 BIB 13 48 1237000100002 TITLE The total neutron cross section of normal uranium in 1237000100003 the energy range from 20 to 1600 keV 1237000100004 AUTHOR (H.H.Barschall,R.K.Adair,C.K.Bockelman,E.R.Graves, 1237000100005 R.L.Henkel,R.E.Peterson) 1237000100006 REFERENCE (R,LA-1060,1950) 1237000100007 REL-REF (M,11249001,R.K.Adair+,J,PR,75,1124,1949) 1237000100008 INSTITUTE (1USAWIS,1USALAS) 1237000100009 FACILITY (VDG,1USAWIS) The Wisconsin electrostatic generator. 1237000100010 INC-SOURCE (P-LI7) Neutrons were obtained by bombarding a 1237000100011 lithium target by protons. The Li target had a 1237000100012 stopping power of 25 keV at the Li(p,n) threshold. 1237000100013 Most of the energy spread of the neutrons was due to 1237000100014 the finite target thickness. 1237000100015 SAMPLE The one-cm thick sample was used at energies below 1237000100016 900 keV, while the 2-cm sample was used above this 1237000100017 energy. Two samples of normal uranium were used, both 1237000100018 circular disks, 1-3/4 inches in diameter. One was one 1237000100019 cm thick and contained 0.0479*10**24 atoms/cm2, the 1237000100020 other was 2 cm thick containing 0.0957*10**24 1237000100021 atoms/cm2. 1237000100022 DETECTOR (BF3) The neutrons were detected by means of B10F3 1237000100023 counter. 1237000100024 ANALYSIS Cross sections were computed assuming an exponential 1237000100025 decrease of neutron intensity in the sample. Neutron 1237000100026 energies were computed from the known value of the 1237000100027 Li(p,n) threshold, i.e., 1.882 MeV. Neutron 1237000100028 energies are taken as those half-way between the 1237000100029 maximum and minimum value of the neutron energy 1237000100030 spread caused by the finite target thickness. 1237000100031 ERR-ANALYS (ERR-S) The resulting statistical error is about +- 1237000100032 0.7 barns at the lowest energies, +-0.5 barns up to 1237000100033 one MeV and +-0.2 barns above one MeV. 1237000100034 CORRECTION The cross sections were corrected for background and 1237000100035 for scattering into the detector (3%) assuming 1237000100036 isotropic scattering. Diffraction scattering was not 1237000100037 taken into account, nor could the increased 1237000100038 sensitivity of the counter for inelastically 1237000100039 scattered neutrons be corrected for. If only elastic 1237000100040 scattering occurred, the correction for diffraction 1237000100041 scattering would increase the cross by 7% at 500 keV. 1237000100042 HISTORY (19760804T) Translated from SCISRS. 1237000100043 (19820519A) Converted to reaction formalism. 1237000100044 (20220304A) BP: Updated to new date formats, lower 1237000100045 case. corrections according last EXFOR rules and 1237000100046 Dict. Added related ref, facility, incoming source, 1237000100047 sample, detector, analysis, error analysis, digitized 1237000100048 data, separated data sets for two slightly different 1237000100049 methods. 1237000100050 ENDBIB 48 0 1237000100051 NOCOMMON 0 0 1237000100052 ENDSUBENT 51 0 1237000199999 SUBENT 12370002 20220304 14981237000200001 BIB 4 9 1237000200002 REACTION (92-U-0(N,TOT),,SIG) 1237000200003 METHOD (TRN) The measurements were simple transmission 1237000200004 experiments in a geometry such that the cross section 1237000200005 for scattering through angles greater than 20 degrees 1237000200006 was measured. The observations were carried out at an 1237000200007 angle of 115 degrees with respect to the incident 1237000200008 protons. 1237000200009 STATUS (CURVE) Fig. 1, page 5. 1237000200010 HISTORY (20220304A) BP: Replaced data. 1237000200011 ENDBIB 9 0 1237000200012 COMMON 2 3 1237000200013 EN-RSL ERR-S 1237000200014 KEV B 1237000200015 15.0 0.7 1237000200016 ENDCOMMON 3 0 1237000200017 DATA 2 8 1237000200018 EN DATA 1237000200019 KEV B 1237000200020 20.199 15.256 1237000200021 41.191 13.008 1237000200022 65.285 12.614 1237000200023 92.808 12.136 1237000200024 114.520 11.574 1237000200025 143.451 11.687 1237000200026 229.416 10.085 1237000200027 265.063 9.691 1237000200028 ENDDATA 10 0 1237000200029 ENDSUBENT 28 0 1237000299999 SUBENT 12370003 20220308 14981237000300001 BIB 4 8 1237000300002 REACTION (92-U-0(N,TOT),,SIG) 1237000300003 METHOD (TRN) The measurements were simple transmission 1237000300004 experiments in a geometry such that the cross section 1237000300005 for scattering through angles greater than 20 degrees 1237000300006 was measured. The neutrons in the forward direction 1237000300007 were used. 1237000300008 STATUS (CURVE) Fig. 1, page 5. 1237000300009 HISTORY (20220304C) BP 1237000300010 ENDBIB 8 0 1237000300011 COMMON 1 3 1237000300012 EN-RSL 1237000300013 KEV 1237000300014 25.0 1237000300015 ENDCOMMON 3 0 1237000300016 DATA 3 52 1237000300017 EN DATA ERR-S 1237000300018 KEV B B 1237000300019 125.869 11.097 0.5 1237000300020 169.891 11.378 0.5 1237000300021 206.466 10.450 0.5 1237000300022 243.148 9.776 0.5 1237000300023 276.533 9.495 0.5 1237000300024 306.823 10.085 0.5 1237000300025 330.845 9.523 0.5 1237000300026 332.927 8.989 0.5 1237000300027 346.211 10.338 0.5 1237000300028 366.384 8.876 0.5 1237000300029 402.390 9.326 0.5 1237000300030 412.632 8.961 0.5 1237000300031 444.921 8.820 0.5 1237000300032 477.138 8.511 0.5 1237000300033 510.559 8.314 0.5 1237000300034 541.657 8.089 0.5 1237000300035 569.600 8.595 0.5 1237000300036 606.594 8.652 0.5 1237000300037 635.106 7.780 0.5 1237000300038 663.797 7.331 0.5 1237000300039 698.684 7.865 0.5 1237000300040 730.685 7.050 0.5 1237000300041 761.735 6.712 0.5 1237000300042 789.535 6.881 0.5 1237000300043 807.128 7.499 0.5 1237000300044 821.016 7.555 0.5 1237000300045 839.333 7.162 0.5 1237000300046 849.575 6.797 0.5 1237000300047 867.121 7.303 0.5 1237000300048 882.548 8.258 0.5 1237000300049 899.230 6.740 0.5 1237000300050 908.688 7.246 0.5 1237000300051 928.353 7.303 0.5 1237000300052 939.558 6.487 0.5 1237000300053 952.447 6.909 0.5 1237000300054 996.517 7.303 0.5 1237000300055 1001.078 7.162 0.2 1237000300056 1018.456 7.274 0.2 1237000300057 1034.534 7.050 0.2 1237000300058 1050.565 6.712 0.2 1237000300059 1085.296 6.881 0.2 1237000300060 1114.239 7.021 0.2 1237000300061 1140.944 7.331 0.2 1237000300062 1171.897 6.769 0.2 1237000300063 1204.378 7.078 0.2 1237000300064 1232.034 6.909 0.2 1237000300065 1264.419 6.993 0.2 1237000300066 1294.325 6.684 0.2 1237000300067 1323.472 7.303 0.2 1237000300068 1352.391 7.387 0.2 1237000300069 1382.190 6.825 0.2 1237000300070 1413.611 7.359 0.2 1237000300071 ENDDATA 54 0 1237000300072 ENDSUBENT 71 0 1237000399999 ENDENTRY 3 0 1237099999999