ENTRY 20385 20110827 22272038500000001 SUBENT 20385001 20110827 22272038500100001 BIB 13 42 2038500100002 TITLE -The energy spectrum of prompt neutrons from the 2038500100003 fission of uranium-235 by 0.40 MeV neutrons.- 2038500100004 AUTHOR (M.M.Islam, H.-H.Knitter) 2038500100005 INSTITUTE (2ZZZGEL) 2038500100006 REFERENCE (J,NSE,50,108,197302) Main reference. Curve of spectrum2038500100007 (W,Knitter,197211) Data of fission neutron spectrum. 2038500100008 (C,71VIENNA,,41,197108) Review of U and Pu data. 2038500100009 REL-REF (I,20394001,H.-H.Knitter+,J,ZP,257,108,197212) Fission 2038500100010 neutron spectrum at 1.50 MeV. See entry 20394. 2038500100011 FACILITY (VDG,2ZZZGEL) 3 MV Van de Graaff accelerator of CBNM 2038500100012 INC-SOURCE (P-T) T(P,N)He-3 reaction, Ti-T target of 2038500100013 495 micro-g/cm2 thickness. 2038500100014 INC-SPECT Energy spread (from target) of +33 to -33 keV 2038500100015 including that due to the sample-to-target geometry. 2038500100016 SAMPLE (92-U-235,0.9315) Enriched to 93.15% in U-235. 2038500100017 .10 cylindrical rings canned in aluminum container of 2038500100018 0.2 mm wall thickness. Outside diameter of the sample 2038500100019 was 3.00 cm, height 2.46 cm. Internal diameters were 2038500100020 2.10 (thick sample) and 2.55cm (thin sample). 2038500100021 .Two samples of different thickness, their weights were2038500100022 161.28 and 88.86 g. 2038500100023 METHOD (TOF) Time of flight, path(detector to sample) = 2038500100024 141 cm. 2038500100025 DETECTOR (SCIN) NE102A plastic scintillator, cylindrical, 2038500100026 5.0 cm dia., 2.5 cm thick, viewed by an AVP 56/03 2038500100027 photomultiplier. Large collimating shields made of 2038500100028 lithium carbonate, paraffin, iron and lead were used. 2038500100029 1 cm lead absorbers in front of the detectors to 2038500100030 suppress the gamma rays from fission and inelastic 2038500100031 scattering. 2038500100032 .For thick-sample measurement, 3 detectors placed at 2038500100033 45, 90 and 135 deg were used. 2038500100034 CORRECTION Corrected for flux attenuation in the sample and for 2038500100035 the energy change of the outgoing fission neutrons 2038500100036 by inelastic scattering and fission processes. 2038500100037 HISTORY (19740116C) 2038500100038 (19741011E) 2038500100039 (19810119A) References added and reactions Re-coded. 2038500100040 (19810213E) 2038500100041 (20110707A) Date is corrected to 6 digit format 2038500100042 Comment upper case converted to lower case 2038500100043 (20110827U) BIB information modified in SAN 002, 003 2038500100044 ENDBIB 42 0 2038500100045 COMMON 1 3 2038500100046 EN 2038500100047 MEV 2038500100048 4.E-01 2038500100049 ENDCOMMON 3 0 2038500100050 ENDSUBENT 49 0 2038500199999 SUBENT 20385002 20110827 22272038500200001 BIB 5 18 2038500200002 REACTION (92-U-235(N,F)0-NN-1,PR,KE) Average fission 2038500200003 neutron energy 2038500200004 ANALYSIS .Fitting by Watt and Maxwellian distribution. 2038500200005 .The Watt distribution: 2038500200006 N(E)=C(exp(-AE)) * (sinh(SQRT(B*E))), where 2038500200007 A =(0.990+-0.027), B =(2.132+-0.274). 2038500200008 ERR-ANALYS (ERR-T) Total errors due to counting statistics and 2038500200009 systematic errors. 2038500200010 (ERR-1) Systematic error from background, 0.5 percent. 2038500200011 (ERR-2) Systematic error from detector efficiency curve2038500200012 was 2 per-cent. 2038500200013 (ERR-3) Systematic error from the shape correction, 2038500200014 1.5 per-cent. 2038500200015 STATUS (TABLE) Table 1 of Nucl.Sci.Eng., vol.50, page 108 2038500200016 (1973) 2038500200017 (DEP,20385003) 2038500200018 HISTORY (19810119A) Error analysis changed. 2038500200019 (20110827U) BIB information modified 2038500200020 ENDBIB 18 0 2038500200021 NOCOMMON 0 0 2038500200022 DATA 5 1 2038500200023 DATA ERR-1 ERR-2 ERR-3 ERR-T 2038500200024 MEV PER-CENT PER-CENT PER-CENT MEV 2038500200025 2.0600E+00 5.0000E-01 2.0000E+00 1.5000E+00 5.0000E-02 2038500200026 ENDDATA 3 0 2038500200027 ENDSUBENT 26 0 2038500299999 SUBENT 20385003 20110827 22272038500300001 BIB 4 9 2038500300002 REACTION (92-U-235(N,F),PR,NU/DE,,REL) Number of fission 2038500300003 neutrons per unit energy interval, arbitrary units. 2038500300004 STATUS (TABLE) Data obtained from Knitter as private 2038500300005 communication, 16-11-1972. 2038500300006 ERR-ANALYS (ERR-S) Errors due to counting statistics and the 2038500300007 uncertainty in the background subtraction. 2038500300008 HISTORY (19810119A) Reaction Re-coded. 2038500300009 (20110827U) REACTION code PR,DE,N changed to PR,NU/DE,,2038500300010 STATUS keyword text corrected 2038500300011 ENDBIB 9 0 2038500300012 NOCOMMON 0 0 2038500300013 DATA 3 91 2038500300014 E DATA ERR-S 2038500300015 MEV ARB-UNITS ARB-UNITS 2038500300016 5.7500E-01 1.8660E+01 5.4000E-01 2038500300017 6.2500E-01 1.9560E+01 5.0000E-01 2038500300018 6.7500E-01 1.9800E+01 5.0000E-01 2038500300019 7.2500E-01 1.9500E+01 4.8000E-01 2038500300020 7.7500E-01 1.9100E+01 4.7000E-01 2038500300021 8.2500E-01 1.9000E+01 4.6000E-01 2038500300022 8.7500E-01 1.9500E+01 4.8000E-01 2038500300023 9.2500E-01 1.8800E+01 4.6000E-01 2038500300024 9.7500E-01 1.8830E+01 4.5000E-01 2038500300025 1.0250E+00 1.8410E+01 4.4000E-01 2038500300026 1.0750E+00 1.8330E+01 4.5000E-01 2038500300027 1.1250E+00 1.7560E+01 4.1000E-01 2038500300028 1.1750E+00 1.7900E+01 4.2000E-01 2038500300029 1.2250E+00 1.8250E+01 4.5000E-01 2038500300030 1.2750E+00 1.7420E+01 4.1000E-01 2038500300031 1.3250E+00 1.6660E+01 4.1000E-01 2038500300032 1.3750E+00 1.6530E+01 3.8000E-01 2038500300033 1.4250E+00 1.6040E+01 3.8000E-01 2038500300034 1.4750E+00 1.5950E+01 3.8000E-01 2038500300035 1.5250E+00 1.5710E+01 4.0000E-01 2038500300036 1.5630E+00 1.6480E+01 4.8000E-01 2038500300037 1.6020E+00 1.5120E+01 4.5000E-01 2038500300038 1.6420E+00 1.5600E+01 4.6000E-01 2038500300039 1.6830E+00 1.5120E+01 4.5000E-01 2038500300040 1.7260E+00 1.5080E+01 4.4000E-01 2038500300041 1.7710E+00 1.3970E+01 4.1000E-01 2038500300042 1.8180E+00 1.4550E+01 4.2000E-01 2038500300043 1.8660E+00 1.3620E+01 4.0000E-01 2038500300044 1.9160E+00 1.3950E+01 4.1000E-01 2038500300045 1.9690E+00 1.3550E+01 3.9000E-01 2038500300046 2.0230E+00 1.3310E+01 3.8000E-01 2038500300047 2.0800E+00 1.2610E+01 3.6000E-01 2038500300048 2.1390E+00 1.2400E+01 3.5000E-01 2038500300049 2.2010E+00 1.1890E+01 3.3000E-01 2038500300050 2.2660E+00 1.1890E+01 3.3000E-01 2038500300051 2.3330E+00 1.1770E+01 3.2000E-01 2038500300052 2.4090E+00 1.1060E+01 3.0000E-01 2038500300053 2.4580E+00 1.0660E+01 2.9000E-01 2038500300054 2.4960E+00 1.0320E+01 2.9000E-01 2038500300055 2.5350E+00 9.7200E+00 2.5000E-01 2038500300056 2.5740E+00 9.7600E+00 2.7000E-01 2038500300057 2.6150E+00 9.1800E+00 2.6000E-01 2038500300058 2.6560E+00 9.5300E+00 2.7000E-01 2038500300059 2.6980E+00 9.2800E+00 2.6000E-01 2038500300060 2.7420E+00 9.4300E+00 2.6000E-01 2038500300061 2.7860E+00 8.7200E+00 2.5000E-01 2038500300062 2.8320E+00 8.7800E+00 2.5000E-01 2038500300063 2.8780E+00 8.5400E+00 2.5000E-01 2038500300064 2.9260E+00 8.4600E+00 2.5000E-01 2038500300065 2.9750E+00 7.5800E+00 2.3000E-01 2038500300066 3.0250E+00 7.6800E+00 2.3000E-01 2038500300067 3.0770E+00 7.3500E+00 2.2000E-01 2038500300068 3.1300E+00 7.3800E+00 2.2000E-01 2038500300069 3.1840E+00 6.8100E+00 2.1000E-01 2038500300070 3.2400E+00 6.9900E+00 2.1000E-01 2038500300071 3.2970E+00 6.6100E+00 2.0000E-01 2038500300072 3.3550E+00 6.3900E+00 1.9000E-01 2038500300073 3.4160E+00 6.1800E+00 1.9000E-01 2038500300074 3.4780E+00 6.1500E+00 1.9000E-01 2038500300075 3.5410E+00 5.9100E+00 1.8000E-01 2038500300076 3.6070E+00 5.4400E+00 1.7000E-01 2038500300077 3.6740E+00 5.1900E+00 1.6000E-01 2038500300078 3.7430E+00 5.2600E+00 1.6000E-01 2038500300079 3.8140E+00 4.6400E+00 1.5000E-01 2038500300080 3.8870E+00 4.6000E+00 1.5000E-01 2038500300081 3.9620E+00 4.4400E+00 1.4000E-01 2038500300082 4.0390E+00 4.3400E+00 1.4000E-01 2038500300083 4.1190E+00 4.2200E+00 1.4000E-01 2038500300084 4.2010E+00 3.7900E+00 1.3000E-01 2038500300085 4.2860E+00 3.5800E+00 1.2000E-01 2038500300086 4.3730E+00 3.4700E+00 1.2000E-01 2038500300087 4.4630E+00 3.2300E+00 1.1000E-01 2038500300088 4.5550E+00 2.9400E+00 1.1000E-01 2038500300089 4.6510E+00 2.9000E+00 1.0000E-01 2038500300090 4.7490E+00 2.6100E+00 1.0000E-01 2038500300091 4.8510E+00 2.3500E+00 9.0000E-02 2038500300092 4.9560E+00 2.4400E+00 9.0000E-02 2038500300093 5.0640E+00 2.1500E+00 9.0000E-02 2038500300094 5.1760E+00 2.1500E+00 9.0000E-02 2038500300095 5.2920E+00 1.7300E+00 8.0000E-02 2038500300096 5.4120E+00 1.8800E+00 8.0000E-02 2038500300097 5.5360E+00 1.5800E+00 7.0000E-02 2038500300098 5.6640E+00 1.4400E+00 7.0000E-02 2038500300099 5.7960E+00 1.4400E+00 7.0000E-02 2038500300100 5.9340E+00 1.2900E+00 7.0000E-02 2038500300101 6.0760E+00 1.2600E+00 6.0000E-02 2038500300102 6.2230E+00 1.1000E+00 6.0000E-02 2038500300103 6.3760E+00 1.0300E+00 6.0000E-02 2038500300104 6.5350E+00 9.2000E-01 5.0000E-02 2038500300105 6.7000E+00 5.5000E-01 4.0000E-02 2038500300106 6.8700E+00 3.9000E-01 4.0000E-02 2038500300107 ENDDATA 93 0 2038500300108 ENDSUBENT 107 0 2038500399999 ENDENTRY 3 0 2038599999999