ENTRY 20427 20080807 22022042700000001 SUBENT 20427001 20080807 22022042700100001 BIB 17 79 2042700100002 INSTITUTE (2GERKFK) 2042700100003 REFERENCE (C,75WASH,2,549,197503) Graph of nu-prompt given as 2042700100004 function of incident neutron energy. 2042700100005 (W,KAEPPELER,197506) Tabulated data. 2042700100006 AUTHOR (F.Kaeppeler, R.E.Bandl) 2042700100007 TITLE -The average number of prompt neutrons from neutron 2042700100008 induced fission of U-235 between 0.2 and 1.4 MeV.- 2042700100009 FACILITY (VDG) 3 MV pulsed Van-de-Graaff accelerator. 2042700100010 Pulse width 1 nsec, average beam current 20 microA at 2042700100011 repetition rate 5 MHz. 2042700100012 INC-SOURCE (P-LI7) Li-7(N,P). Collimated neutron beam. 2042700100013 INC-SPECT The metallic Li-targets thickness was such, that 2042700100014 neutron energy spread deltaEn was less 4%. 2042700100015 SAMPLE Two uranium acetate layers less than 0.5 millig/cm**2 2042700100016 in fission chamber at 56 and 63 cm flight path 2042700100017 and U-235 metal disk of 0.15 millimeter thick, 2042700100018 70 millimeter diameter at 74 cm flight path. 2042700100019 DETECTOR (SCIN) -Gas scintillation fission counter, containing 2042700100020 two thin samples of U-235, divided by samples into 2042700100021 optically decoupled thirds each inspected by 56 DUVP 2042700100022 photomultipliers. 2042700100023 -Fission neutron detector PM XP 1040, placed at 2042700100024 12.5 cm distance from sample. 2042700100025 Both detectors and the samples were shielded against 2042700100026 slow, roomscattered neutrons by Cd-sheets to reduce 2042700100027 the time-independent background. 2042700100028 (GLASD) Li-6-glass detector at 130 cm from target for 2042700100029 neutron spectrum determination and as monitor for 2042700100030 neutron yield. 2042700100031 Calibration procedure was done by strong Am-Be neutron 2042700100032 source located at 3m distance to measure efficiency. 2042700100033 METHOD (TOF) Time-of-flight. Overall time resolution 2.5 nsec.2042700100034 (COINC) Coincidence between two thirds to register 2042700100035 a fission event. 2042700100036 (PSD) Pulse shape discrimination against gamma 2042700100037 radiation. 2042700100038 MONITOR (92-U-235(N,F),PR,NU,,AV) Integral from 225 to 1363keV2042700100039 of NUp values recommended by F.Manero 2042700100040 and V.A.Konshin, Atomic Energy Review 10, IAEA, 2042700100041 Vienna(1972),P.637, was used for normalization. 2042700100042 MONIT-REF (,P.Manero+,J,REA,10,637,1972) 2042700100043 PART-DET (FF) Fission-fragments 2042700100044 (N) Fission-neutrons 2042700100045 Detailed description of detection given in reference. 2042700100046 ANALYSIS TOF spectra of three samples and the pulse height 2042700100047 distribution of the fission neutron detector for max. 2042700100048 energy run at 1363+-35 keV were used. 2042700100049 Prompt neutron yield was derived from integrated peaks2042700100050 in TOF spectra. 2042700100051 CORRECTION Carefully considered,see Table 1 of reference. 2042700100052 Correction for: 2042700100053 -Fission neutron detector efficiency and increase of 2042700100054 fragment temperature - 5% (max.), 2042700100055 -Isotopic composition - 1.5% (max.), 2042700100056 -Multiple scattering - 1.5% (max.), 2042700100057 -Self shielding and fission neutron angular 2042700100058 distribution - 0.8% (max.). 2042700100059 Background considerations concerning the fission 2042700100060 neutron detector were made. 2042700100061 ERR-ANALYS (ERR-SYS) Systematic uncertainty due to background and 2042700100062 corrections was 0.6 %. 2042700100063 (ERR-S) Max error of counting statistics 1.1% . 2042700100064 Min error of counting statistics is 0.6% 2042700100065 ERR-SYS and ERR-S correspond to one standard deviation.2042700100066 (ERR-1) Uncertainty of correction for fission neutron 2042700100067 detector efficiency and increase of fragment 2042700100068 temperature. 2042700100069 (ERR-2) Uncertainty of correction for isotopic 2042700100070 composition. Maximal. 2042700100071 (ERR-3) Uncertainty of correction for multiple 2042700100072 scattering . Maximal. 2042700100073 (ERR-4) Uncertainty of correction for self shielding 2042700100074 and fission neutron angular distribution. Max. 2042700100075 HISTORY (19750707C) 2042700100076 (19750925E) 2042700100077 (20070601A) Date is corrected. Error structure given. 2042700100078 (20070601U) Last corrections have been done. 2042700100079 (20080807A) M.M. BIB and COMMON information was added. 2042700100080 Data units of Subent 002 were corrected. 2042700100081 ENDBIB 79 0 2042700100082 COMMON 6 3 2042700100083 ERR-S ERR-SYS ERR-1 ERR-2 ERR-3 ERR-4 2042700100084 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2042700100085 1.1 0.6 0.5 0.2 0.2 0.2 2042700100086 ENDCOMMON 3 0 2042700100087 ENDSUBENT 86 0 2042700199999 SUBENT 20427002 20080807 22022042700200001 BIB 3 12 2042700200002 REACTION (92-U-235(N,F),PR,NU) 2042700200003 HISTORY (20070601A) Data units corrected, NO-DIM to PC/FIS 2042700200004 (20080807A) M.M. DATA units were corrected from 2042700200005 PC/FIS into PRT/FIS in according to Fig.3 of 1-st Ref.2042700200006 DATA-ERR units were corrected from PC/FIS into PER-CENT2042700200007 in according to error bars of overall uncertainties 2042700200008 given on Fig.3 of 1-st Reference. 2042700200009 DATA-ERR was changed into ERR-T in according to text 2042700200010 of 1-st Reference, p.552 and Fig.3 of 1-st Reference. 2042700200011 (See also ERR-ANALYS). 2042700200012 STATUS (TABLE) Data from authors - see second Reference. 2042700200013 Data are presented on Fig.3 of 1-st Reference. 2042700200014 ENDBIB 12 0 2042700200015 NOCOMMON 0 0 2042700200016 DATA 4 22 2042700200017 EN EN-RSL DATA ERR-T 2042700200018 KEV KEV PRT/FIS PER-CENT 2042700200019 2.2500E+02 1.0000E+01 2.4760E+00 9.0000E-01 2042700200020 2.7100E+02 1.2000E+01 2.4540E+00 1.0000E+00 2042700200021 3.2300E+02 1.8000E+01 2.4690E+00 7.0000E-01 2042700200022 3.6400E+02 1.8000E+01 2.4960E+00 1.2000E+00 2042700200023 4.1900E+02 1.7000E+01 2.4770E+00 7.0000E-01 2042700200024 4.6300E+02 2.2000E+01 2.4880E+00 1.1000E+00 2042700200025 5.2200E+02 1.6000E+01 2.5160E+00 9.0000E-01 2042700200026 6.1600E+02 2.2000E+01 2.4560E+00 7.0000E-01 2042700200027 6.7300E+02 2.2000E+01 2.4870E+00 7.0000E-01 2042700200028 7.2300E+02 2.4000E+01 2.4520E+00 7.0000E-01 2042700200029 7.8200E+02 2.2000E+01 2.5100E+00 1.0000E+00 2042700200030 8.3200E+02 2.0000E+01 2.5170E+00 1.0000E+00 2042700200031 8.8700E+02 2.3000E+01 2.5160E+00 1.0000E+00 2042700200032 9.3000E+02 2.5000E+01 2.4750E+00 1.0000E+00 2042700200033 9.8800E+02 2.7000E+01 2.4690E+00 1.0000E+00 2042700200034 1.0460E+03 3.5000E+01 2.5090E+00 7.0000E-01 2042700200035 1.0970E+03 2.6000E+01 2.5360E+00 1.1000E+00 2042700200036 1.1480E+03 2.7000E+01 2.5300E+00 1.1000E+00 2042700200037 1.1990E+03 3.4000E+01 2.5670E+00 1.1000E+00 2042700200038 1.2650E+03 3.0000E+01 2.5400E+00 1.1000E+00 2042700200039 1.3230E+03 4.0000E+01 2.5480E+00 1.0000E+00 2042700200040 1.3630E+03 3.5000E+01 2.5310E+00 1.1000E+00 2042700200041 ENDDATA 24 0 2042700200042 ENDSUBENT 41 0 2042700299999 ENDENTRY 2 0 2042799999999