ENTRY 20764 20120718 22322076400000001 SUBENT 20764001 20120718 22322076400100001 BIB 17 135 2076400100002 INSTITUTE (2ZZZGEL) 2076400100003 REFERENCE (J,AKE,33,205,1979) Comments and data given. 2076400100004 Prepublished in CBNM reports under number 2076400100005 CBNM-VG 25/78 2076400100006 (W,KNITTER,19780428) Attached sheets with preliminary 2076400100007 data which are given in subentry in this entry. 2076400100008 REL-REF (I,,C.Budtz-Jorgensen+,J,NIM,154,121,1978) Information 2076400100009 about facilities, and instrumentation. 2076400100010 AUTHOR (H.H.Knitter,C.Budtz-Jorgensen) 2076400100011 TITLE Measurement of the neutron induced fission 2076400100012 cross-section of Am-241 from 100 eV to 5.3 MeV 2076400100013 FACILITY (VDG,2ZZZGEL) 7 MB CBNM accelerator at Geel. 2076400100014 -For neutron energies above 4.5 MeV,pulse mode gave 2076400100015 deuterons 4-micro-A-average current,1.5 nsec pulse 2076400100016 width,2.5 MHz repetition frequency.See 1st n-source. 2076400100017 -From 1 to 4.5 MeV n-energies,pulsed mode with the 2076400100018 same characteristics as above gave protons 2076400100019 2nd n-source. 2076400100020 -From 0.153 to 1.3 MeV, dc-mode gave P with a 80 Watts2076400100021 power.See 3rd n-source. While pulsed mode allowed a 2076400100022 neutron TOF spectra measurement. 2076400100023 -For neutron energies below 300 keV,pulsed mode gave 2076400100024 protons.See 3rd n-source. 2076400100025 (LINAC,2ZZZGEL) A 5cm collimated neutron beam of the 2076400100026 electron LINAC of the CBNM,operated with a pulse width2076400100027 of 4.4 nsec,a repetition frequency of 800 Hz and an 2076400100028 average beam power of 4KW at 100 MeV. 2076400100029 INC-SOURCE (D-D) For n-energies above 4.5 MeV monoenergetic 2076400100030 neutrons deuterium gas was employed. 2076400100031 (P-T) For n-energy range from 1 to 4.5 MeV 2076400100032 tritium loaded Ti-layers on 0.3 mm thick silver 2076400100033 backings were used as targets. Monoenergetic neutrons.2076400100034 (P-LI7) For n-energy range from 153 to 1300 keV. 2076400100035 Air-cooled targets made of LiF on 0.3 mm thick silver 2076400100036 backings. Monoenergetic neutrons. 2076400100037 For n-energies below 300 keV target was a 1 mm 2076400100038 thick metallic lithium disc covered by a 50 microns 2076400100039 thick Al-foil. Broad spectrum of neutrons was 2076400100040 produced. 2076400100041 .The neutron beam of CBNM Linac gave neutrons in the 2076400100042 range of energy from 1 eV to 2.5 MeV. 2076400100043 SAMPLE .Two 2.5 cm diam samples of chemically pure Am, were 2076400100044 used in two identical ionization chambers, back to 2076400100045 back with two U-235 samples. 2076400100046 .The relevant data are following (C means chamber No). 2076400100047 C Am (mg) U-235 (mg) Am-241 (%) Am-243 (%) 2076400100048 1 0.867+-.009 1.482+-.028 99.995+-.005 0.005+-.005 2076400100049 2 4.01 +-.05 1.551+-.028 99.995+-.005 0.005+-.005 . 2076400100050 .Pu-239 has been identified as major contaminant with 2076400100051 a relative number of Pu-239 nuclei of (0.69+-.10)%. 2076400100052 METHOD (TOF) 2076400100053 (EXTB) 2076400100054 (MOSEP) 2076400100055 .Two chambers were used(1 and 2),chamber1 for 2076400100056 monoenergetic source measurements,chamber2 for 2076400100057 white-source measurements. 2076400100058 .For measurements carried out with VdG above 300 keV, 2076400100059 in pulsed mode,a time correlated and a 2076400100060 time-uncorrelated spectrum was recorded during the 2076400100061 same measuring time. For those in dc-mode only 2076400100062 foreground spectra were registered. 2076400100063 .For measurements with VDG below 300 keV in pulsed 2076400100064 mode the time of flight spectra were recorded. 2076400100065 .For Linac measurements TOF spectra were recorded. 2076400100066 .Above 2 keV U-235 chamber part was used to determine 2076400100067 the energy dependence of the neutron flux. Below an 2076400100068 ionization chamber loaded with a sample of LiF was 2076400100069 used to determine the energy dep. of neutron flux. 2076400100070 For resonance measurement below(20 eV),U-235 was 2076400100071 used again. 2076400100072 DETECTOR (IOCH ) Single layers of U-235 and Am-241 mounted back 2076400100073 to back in a special double-function ionization 2076400100074 chamber with an intrinsic suppression of alpha 2076400100075 background.The lower part of the chamber was used for 2076400100076 U-235 fission-fragment detection. The upper was used 2076400100077 as a parallel plate chamber for Am-241 FF detection. 2076400100078 A collimator was placed above the sample. 2076400100079 Chamber was positioned at 6 or 20 cm from the neutron 2076400100080 producing target for monoenergetic or white-source 2076400100081 measurements,respectively,at zero deg with respect to 2076400100082 the incident ion beam of the accelerator. 2076400100083 See for more details NIM. 2076400100084 .Neutron detector positioned at the zero deg direction,2076400100085 at a distance from neutron prod.Target chosen between 2076400100086 2.8 and 11.3 m,according to n-energy and n-energy 2076400100087 spread to be measured. No other information given. 2076400100088 ANALYSIS .The fission cross sections of Am-241 was obtained 2076400100089 according to the following expression 2076400100090 sig241(E) = N(U)*FA(E)*C(E)*Cg*sig235(E) 2076400100091 --------------------------- - C239(E) 2076400100092 N(A)*FU(E)*Epsi*Ct*FU(E) 2076400100093 where - N(U),N(A) numbers of U-235 and Am-241 nuclei. 2076400100094 - FA(E),FU(E) numbers of detected fission 2076400100095 events at E-energy for Am and U,respectively. 2076400100096 - C(E), Ct correction factors for angular 2076400100097 anisotropy effects and fission layer geometry 2076400100098 effects. 2076400100099 - Cg corrects for the difference in geometry of 2076400100100 the two fission layers with respect to the 2076400100101 neutron target. It includes also the neutron 2076400100102 absorption by the backing material. 2076400100103 - Epsi,collimator efficiency. 2076400100104 - Sig235(E),U-235 ENDF/B-IV standard fission cs.2076400100105 - C239(E),taken from Pu-239/U-235 ENDF/B-IV 2076400100106 fission cs.evaluation of Poenitz et al. Sup. 2076400100107 to NEANDC(US)-199/l,page 83. 2076400100108 (AREA ) Fission widths were calculated from fission 2076400100109 area using neutron widths and total widths given by 2076400100110 Derrien and Lucas,75Wash,vol.2,page 637. 2076400100111 CORRECTION Ratio ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2076400100112 was used for correction 2076400100113 .Data were corrected for time-correlated and time 2076400100114 uncorrelated background,for Pu-239 contamination. 2076400100115 PART-DET (FF) For detection of fission events. 2076400100116 (PN) For fission width measurements. 2076400100117 (N) For spectra measurement. 2076400100118 COMMENT .Comparison with other data made,and curves given. 2076400100119 .This compilation includes the ratios 2076400100120 measured at the VDG,and presented in AKE,78,as well 2076400100121 as the absolute value of Am-241 fission cross-section 2076400100122 given in private communication(Knitter 780428) by the 2076400100123 author,each in different subentries. 2076400100124 STATUS (TABLE) .Data taken from AKE,78 and from private 2076400100125 communication 2076400100126 ERR-ANALYS (DATA-ERR) Total error given. 2076400100127 HISTORY (19780910C) 2076400100128 (19781024E) 2076400100129 (19860808A) HH main reference corrected 2076400100130 (19860822E) 2076400100131 (20061018A) Date is corrected. DATA-ERR changed to 2076400100132 ERR-T. EN-ERR changed to EN-RSL. 2076400100133 (20120716U) SD: ref. was changed (NIM,78,1,197812 -> 2076400100134 NIM,154,121,1978) and moved to REL-REF. 2076400100135 ERR-T renamed on DATA-ERR in all Subents according 2076400100136 to last EXFOR rules. Cosmetic corrections. 2076400100137 ENDBIB 135 0 2076400100138 NOCOMMON 0 0 2076400100139 ENDSUBENT 138 0 2076400199999 SUBENT 20764002 20120718 22322076400200001 BIB 6 9 2076400200002 REACTION (95-AM-241(N,F),,SIG) 2076400200003 MONITOR (92-U-235(N,F),,SIG) 2076400200004 MONIT-REF (,,3,ENDF/B-IV,1261,1974) 2076400200005 COMMENT .Data obtained by TOF method at VDG,and derived from 2076400200006 ratios and the mean of ENDFB/IV data files, 2076400200007 see ANALYSIS 2076400200008 STATUS (TABLE) Data taken from private communication, Knitter.2076400200009 (DEP,20764005) See comments 2076400200010 HISTORY (20061018U) Column order changed 2076400200011 ENDBIB 9 0 2076400200012 NOCOMMON 0 0 2076400200013 DATA 5 17 2076400200014 EN EN-RSL DATA DATA-ERR MONIT 2076400200015 KEV KEV MB MB B 2076400200016 6.0000E+00 1.0000E+00 5.3680E+01 2.8046E+01 3.2400E+00 2076400200017 8.5000E+00 1.5000E+00 2.0625E+01 1.6163E+01 3.0840E+00 2076400200018 1.2500E+01 2.5000E+00 2.0850E+01 8.9736E+00 2.7185E+00 2076400200019 1.7500E+01 2.5000E+00 1.9570E+01 6.7781E+00 2.4555E+00 2076400200020 2.5000E+01 5.0000E+00 2.3672E+01 4.9695E+00 2.1935E+00 2076400200021 3.5000E+01 5.0000E+00 1.9471E+01 4.5808E+00 1.9885E+00 2076400200022 4.5000E+01 5.0000E+00 2.1271E+01 4.4696E+00 1.8725E+00 2076400200023 5.5000E+01 5.0000E+00 1.8575E+01 4.4961E+00 1.7895E+00 2076400200024 6.5000E+01 5.0000E+00 2.2216E+01 4.4977E+00 1.7142E+00 2076400200025 7.5000E+01 5.0000E+00 2.3647E+01 4.4969E+00 1.6467E+00 2076400200026 8.5000E+01 5.0000E+00 2.0361E+01 4.4913E+00 1.6185E+00 2076400200027 9.5000E+01 5.0000E+00 2.2651E+01 4.7286E+00 1.6295E+00 2076400200028 1.1000E+02 1.0000E+01 2.1366E+01 4.2885E+00 1.5555E+00 2076400200029 1.3500E+02 1.5000E+01 2.3301E+01 4.1209E+00 1.4960E+00 2076400200030 1.7500E+02 2.5000E+01 2.8121E+01 4.0551E+00 1.4032E+00 2076400200031 2.2500E+02 2.5000E+01 3.1529E+01 4.2616E+00 1.3120E+00 2076400200032 2.7500E+02 2.5000E+01 3.9277E+01 4.7139E+00 1.2975E+00 2076400200033 ENDDATA 19 0 2076400200034 ENDSUBENT 33 0 2076400299999 SUBENT 20764003 20120718 22322076400300001 BIB 5 8 2076400300002 REACTION (95-AM-241(N,F),,SIG) 2076400300003 MONITOR (92-U-235(N,F),,SIG) 2076400300004 COMMENT .Data obtained by using monoenergetic neutrons from 2076400300005 VDG accelerator,by normalizing raw data with U-235 2076400300006 fission cs. and correcting from Pu-239 contamination 2076400300007 using evaluated data. Pu-239 data were not given. 2076400300008 STATUS (DEP,20764004) Data taken from private com.,Knitter. 2076400300009 HISTORY (20061018U) Column order corrected 2076400300010 ENDBIB 8 0 2076400300011 NOCOMMON 0 0 2076400300012 DATA 4 78 2076400300013 EN DATA DATA-ERR MONIT 2076400300014 KEV MB MB B 2076400300015 1.5300E+02 2.1427E+01 4.8561E+00 1.4526E+00 2076400300016 1.6300E+02 1.9702E+01 6.4333E+00 1.4323E+00 2076400300017 1.9000E+02 1.9072E+01 6.0040E+00 1.3725E+00 2076400300018 2.1600E+02 2.6626E+01 4.7729E+00 1.3252E+00 2076400300019 2.4500E+02 2.8271E+01 7.2376E+00 1.3090E+00 2076400300020 2.7000E+02 3.4333E+01 6.3479E+00 1.3000E+00 2076400300021 3.3900E+02 4.7630E+01 7.0670E+00 1.2296E+00 2076400300022 3.9000E+02 4.7203E+01 6.1616E+00 1.2185E+00 2076400300023 4.2500E+02 6.6754E+01 6.1446E+00 1.2077E+00 2076400300024 4.5800E+02 7.2196E+01 5.5563E+00 1.1912E+00 2076400300025 4.9000E+02 9.6019E+01 6.5218E+00 1.1760E+00 2076400300026 5.1900E+02 1.0622E+02 7.6564E+00 1.1644E+00 2076400300027 5.4800E+02 1.1998E+02 8.2419E+00 1.1580E+00 2076400300028 5.7400E+02 1.4434E+02 7.6289E+00 1.1546E+00 2076400300029 6.0000E+02 1.8790E+02 1.0427E+01 1.1520E+00 2076400300030 6.2800E+02 2.0973E+02 8.2198E+01 1.1474E+00 2076400300031 6.5500E+02 2.7496E+02 1.8707E+01 1.1430E+00 2076400300032 6.8000E+02 2.9551E+02 1.3141E+01 1.1390E+00 2076400300033 7.0500E+02 3.5978E+02 1.7466E+01 1.1337E+00 2076400300034 7.3300E+02 4.2692E+02 2.1815E+01 1.1287E+00 2076400300035 7.6000E+02 5.1791E+02 2.4028E+01 1.1280E+00 2076400300036 7.8000E+02 6.0350E+02 2.6305E+01 1.1300E+00 2076400300037 8.0100E+02 6.8001E+02 2.5268E+01 1.1333E+00 2076400300038 8.1600E+02 6.7185E+02 2.9885E+01 1.1386E+00 2076400300039 8.3100E+02 7.6045E+02 3.1138E+01 1.1433E+00 2076400300040 8.6000E+02 8.2740E+02 2.4702E+01 1.1600E+00 2076400300041 8.6200E+02 7.9404E+02 2.8149E+01 1.1604E+00 2076400300042 8.7400E+02 8.3180E+02 3.0507E+01 1.1628E+00 2076400300043 8.8600E+02 9.9008E+02 3.7566E+01 1.1670E+00 2076400300044 8.9800E+02 9.9289E+02 2.8446E+01 1.1730E+00 2076400300045 9.1000E+02 1.1041E+03 6.0267E+01 1.1790E+00 2076400300046 9.3700E+02 1.0369E+03 4.1939E+01 1.1925E+00 2076400300047 9.6300E+02 1.1052E+03 4.9609E+01 1.2058E+00 2076400300048 9.9200E+02 1.2157E+03 4.2935E+01 1.2210E+00 2076400300049 1.0230E+03 1.2949E+03 5.0698E+01 1.2323E+00 2076400300050 1.0520E+03 1.3863E+03 4.9831E+01 1.2413E+00 2076400300051 1.0850E+03 1.3942E+03 4.8826E+01 1.2473E+00 2076400300052 1.1180E+03 1.5056E+03 6.2733E+01 1.2518E+00 2076400300053 1.1630E+03 1.5643E+03 5.0413E+01 1.2557E+00 2076400300054 1.1900E+03 1.5574E+03 5.5492E+01 1.2574E+00 2076400300055 1.2130E+03 1.7112E+03 5.8017E+01 1.2577E+00 2076400300056 1.2180E+03 1.6233E+03 5.5504E+01 1.2576E+00 2076400300057 1.2700E+03 1.6762E+03 4.2930E+01 1.2561E+00 2076400300058 1.3100E+03 1.7515E+03 4.1628E+01 1.2544E+00 2076400300059 1.4130E+03 1.7572E+03 3.9000E+01 1.2497E+00 2076400300060 1.5160E+03 1.8280E+03 3.7812E+01 1.2512E+00 2076400300061 1.6220E+03 1.8217E+03 3.5556E+01 1.2591E+00 2076400300062 1.7170E+03 1.8068E+03 1.9517E+01 1.2636E+00 2076400300063 1.8210E+03 1.7952E+03 2.7037E+01 1.2680E+00 2076400300064 1.9270E+03 1.7646E+03 3.2159E+01 1.2725E+00 2076400300065 2.0270E+03 1.8035E+03 2.9697E+01 1.2748E+00 2076400300066 2.1100E+03 1.7852E+03 2.5974E+01 1.2772E+00 2076400300067 2.2290E+03 1.8121E+03 2.9788E+01 1.2790E+00 2076400300068 2.4330E+03 1.8717E+03 3.1014E+01 1.2776E+00 2076400300069 2.5320E+03 1.8586E+03 3.0901E+01 1.2730E+00 2076400300070 2.6390E+03 1.8766E+03 3.3222E+01 1.2654E+00 2076400300071 2.7390E+03 1.8356E+03 3.4231E+01 1.2564E+00 2076400300072 2.8280E+03 1.8385E+03 1.9265E+01 1.2482E+00 2076400300073 2.9350E+03 1.8368E+03 3.4951E+01 1.2378E+00 2076400300074 3.0240E+03 1.8590E+03 3.4719E+01 1.2296E+00 2076400300075 3.1160E+03 1.8424E+03 3.5666E+01 1.2202E+00 2076400300076 3.2100E+03 1.8789E+03 4.0174E+01 1.2100E+00 2076400300077 3.3090E+03 1.8361E+03 4.3430E+01 1.2001E+00 2076400300078 3.4150E+03 1.8595E+03 3.3623E+01 1.1906E+00 2076400300079 3.5250E+03 1.7708E+03 3.3366E+01 1.1815E+00 2076400300080 3.6140E+03 1.7698E+03 3.4382E+01 1.1761E+00 2076400300081 3.7170E+03 1.8357E+03 5.5134E+01 1.1694E+00 2076400300082 3.8230E+03 1.8237E+03 3.9709E+01 1.1610E+00 2076400300083 3.8690E+03 1.7756E+03 3.9647E+01 1.1592E+00 2076400300084 4.0300E+03 1.8133E+03 3.9260E+01 1.1479E+00 2076400300085 4.1170E+03 1.8510E+03 4.0199E+01 1.1421E+00 2076400300086 4.2440E+03 1.8011E+03 4.1058E+01 1.1344E+00 2076400300087 4.3690E+03 1.7615E+03 4.1893E+01 1.1265E+00 2076400300088 4.4550E+03 1.8108E+03 4.5084E+01 1.1222E+00 2076400300089 4.5290E+03 1.7022E+03 2.2745E+01 1.1179E+00 2076400300090 4.7530E+03 1.6755E+03 4.7687E+01 1.1048E+00 2076400300091 5.0280E+03 1.7109E+03 5.6978E+01 1.0928E+00 2076400300092 5.3430E+03 1.7650E+03 7.2121E+01 1.0747E+00 2076400300093 ENDDATA 80 0 2076400300094 ENDSUBENT 93 0 2076400399999 SUBENT 20764004 20120718 22322076400400001 BIB 3 4 2076400400002 REACTION ((95-AM-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2076400400003 COMMENT .Data obtained by using monoenergetic neutrons from 2076400400004 VDG accelerator. 2076400400005 STATUS (TABLE) .Data taken from Tbl.2 of AKE,78. 2076400400006 ENDBIB 4 0 2076400400007 NOCOMMON 0 0 2076400400008 DATA 3 79 2076400400009 EN DATA DATA-ERR 2076400400010 MEV NO-DIM NO-DIM 2076400400011 1.5300E-01 1.6480E-02 2.4600E-03 2076400400012 1.6300E-01 1.5480E-02 3.9200E-03 2076400400013 1.9000E-01 1.5660E-02 3.7300E-03 2076400400014 2.1600E-01 2.2050E-02 2.6800E-03 2076400400015 2.4500E-01 2.3630E-02 5.0400E-03 2076400400016 2.7000E-01 2.8590E-02 4.2400E-03 2076400400017 3.3900E-01 4.1350E-02 5.1600E-03 2076400400018 3.9000E-01 4.1400E-02 4.2800E-03 2076400400019 4.2500E-01 5.8380E-02 4.2800E-03 2076400400020 4.5800E-01 6.3880E-02 3.7000E-03 2076400400021 4.9000E-01 8.5480E-02 4.7800E-03 2076400400022 5.1900E-01 9.5320E-02 5.9800E-03 2076400400023 5.4800E-01 1.0800E-01 6.5900E-03 2076400400024 5.7400E-01 1.3000E-01 5.9900E-03 2076400400025 6.0000E-01 1.6910E-01 8.7100E-03 2076400400026 6.2800E-01 1.8920E-01 6.6000E-03 2076400400027 6.5500E-01 2.4850E-01 1.6400E-02 2076400400028 6.8000E-01 2.6790E-01 1.1300E-02 2076400400029 7.0500E-01 3.2730E-01 1.5400E-02 2076400400030 7.3300E-01 3.8980E-01 1.9500E-02 2076400400031 7.6000E-01 4.7270E-01 2.1500E-02 2076400400032 7.8000E-01 5.4960E-01 2.3600E-02 2076400400033 8.0100E-01 6.1720E-01 2.2600E-02 2076400400034 8.1600E-01 6.0700E-01 2.6700E-02 2076400400035 8.3100E-01 6.8400E-01 2.7700E-02 2076400400036 8.6000E-01 7.3340E-01 2.1500E-02 2076400400037 8.6200E-01 7.0360E-01 2.4600E-02 2076400400038 8.7400E-01 7.3550E-01 2.6700E-02 2076400400039 8.8600E-01 8.7190E-01 3.2800E-02 2076400400040 8.8600E-01 8.0220E-01 2.6600E-02 2076400400041 8.9800E-01 8.6990E-01 2.4600E-02 2076400400042 9.1000E-01 9.6220E-01 5.2300E-02 2076400400043 9.3700E-01 8.9360E-01 3.5900E-02 2076400400044 9.6300E-01 9.4190E-01 4.2000E-02 2076400400045 9.9200E-01 1.0220E+00 3.5900E-02 2076400400046 1.0200E+00 1.0790E+00 4.2000E-02 2076400400047 1.0500E+00 1.1470E+00 4.1000E-02 2076400400048 1.0800E+00 1.1480E+00 4.0000E-02 2076400400049 1.1100E+00 1.2350E+00 5.1200E-02 2076400400050 1.1600E+00 1.2790E+00 4.1000E-02 2076400400051 1.1900E+00 1.2720E+00 4.5100E-02 2076400400052 1.2100E+00 1.3970E+00 4.7100E-02 2076400400053 1.2100E+00 1.3250E+00 4.5100E-02 2076400400054 1.2700E+00 1.3700E+00 3.4800E-02 2076400400055 1.3100E+00 1.4330E+00 3.3800E-02 2076400400056 1.4100E+00 1.4430E+00 3.1800E-02 2076400400057 1.5100E+00 1.5000E+00 3.0700E-02 2076400400058 1.6200E+00 1.4850E+00 2.8700E-02 2076400400059 1.7100E+00 1.4680E+00 1.5400E-02 2076400400060 1.8200E+00 1.4530E+00 2.1500E-02 2076400400061 1.9200E+00 1.4240E+00 2.5600E-02 2076400400062 2.0200E+00 1.4520E+00 2.3600E-02 2076400400063 2.1100E+00 1.4350E+00 2.0500E-02 2076400400064 2.2200E+00 1.4540E+00 2.3600E-02 2076400400065 2.4300E+00 1.5040E+00 2.4600E-02 2076400400066 2.5300E+00 1.4990E+00 2.4600E-02 2076400400067 2.6300E+00 1.5220E+00 2.6700E-02 2076400400068 2.7300E+00 1.5000E+00 2.7700E-02 2076400400069 2.8200E+00 1.5120E+00 1.5400E-02 2076400400070 2.9300E+00 1.5230E+00 2.8700E-02 2076400400071 3.0200E+00 1.5520E+00 2.8700E-02 2076400400072 3.1100E+00 1.5500E+00 2.9700E-02 2076400400073 3.2100E+00 1.5940E+00 3.3800E-02 2076400400074 3.3000E+00 1.5700E+00 3.6900E-02 2076400400075 3.4100E+00 1.6030E+00 2.8700E-02 2076400400076 3.5200E+00 1.5390E+00 2.8700E-02 2076400400077 3.6100E+00 1.5450E+00 2.9700E-02 2076400400078 3.7100E+00 1.6110E+00 4.8200E-02 2076400400079 3.8200E+00 1.6120E+00 3.4800E-02 2076400400080 3.8600E+00 1.5720E+00 3.4800E-02 2076400400081 4.0300E+00 1.6220E+00 3.4800E-02 2076400400082 4.1100E+00 1.6640E+00 3.5900E-02 2076400400083 4.2400E+00 1.6300E+00 3.6900E-02 2076400400084 4.3600E+00 1.6050E+00 3.7900E-02 2076400400085 4.4500E+00 1.6560E+00 4.1000E-02 2076400400086 4.5200E+00 1.5630E+00 2.0500E-02 2076400400087 4.7500E+00 1.5570E+00 4.4100E-02 2076400400088 5.0200E+00 1.6070E+00 5.3300E-02 2076400400089 5.3400E+00 1.6860E+00 6.8700E-02 2076400400090 ENDDATA 81 0 2076400400091 ENDSUBENT 90 0 2076400499999 SUBENT 20764005 20120718 22322076400500001 BIB 4 5 2076400500002 REACTION ((95-AM-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2076400500003 COMMENT .Data obtained by the TOF method at the VDG. 2076400500004 STATUS (TABLE) .Data taken from Tbl.3 of AKE,78. 2076400500005 HISTORY (20061018A) Three data values corrected in accordance 2076400500006 to Table 3 of main reference 2076400500007 ENDBIB 5 0 2076400500008 NOCOMMON 0 0 2076400500009 DATA 4 17 2076400500010 EN EN-RSL DATA DATA-ERR 2076400500011 KEV KEV NO-DIM NO-DIM 2076400500012 6.0000E+00 1.0000E+00 1.7870E-02 8.7400E-03 2076400500013 8.5000E+00 1.5000E+00 7.7080E-03 5.1600E-03 2076400500014 1.2500E+01 2.5000E+00 8.7180E-03 3.0300E-03 2076400500015 1.7500E+01 2.5000E+00 9.0750E-03 2.3500E-03 2076400500016 2.5000E+01 5.0000E-01 1.2030E-02 1.5900E-03 2076400500017 3.5000E+01 5.0000E-01 1.1070E-02 1.5300E-03 2076400500018 4.5000E+01 5.0000E-01 1.2730E-02 1.5500E-03 2076400500019 5.5000E+01 5.0000E-01 1.1770E-02 1.6500E-03 2076400500020 6.5000E+01 5.0000E-01 1.4450E-02 1.7500E-03 2076400500021 7.5000E+01 5.0000E-01 1.5920E-02 1.8500E-03 2076400500022 8.5000E+01 5.0000E-01 1.4120E-02 1.8700E-03 2076400500023 9.5000E+01 5.0000E-01 1.5520E-02 1.9700E-03 2076400500024 1.1000E+02 1.0000E+01 1.5400E-02 1.6400E-03 2076400500025 1.3500E+02 1.5000E+01 1.7310E-02 1.5700E-03 2076400500026 1.7500E+02 2.5000E+01 2.1940E-02 1.6700E-03 2076400500027 2.2500E+02 2.5000E+01 2.6100E-02 2.1300E-03 2076400500028 2.7500E+02 2.5000E+01 3.2560E-02 2.6000E-03 2076400500029 ENDDATA 19 0 2076400500030 ENDSUBENT 29 0 2076400599999 SUBENT 20764006 20120718 22322076400600001 BIB 4 4 2076400600002 REACTION ((95-AM-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2076400600003 COMMENT .Data obtained by TOF method at LINAC 2076400600004 STATUS (TABLE) .Data taken from Tbl.4 of AKE,78. 2076400600005 HISTORY (20120718A) SD: First value in DATA col. was corrected.2076400600006 ENDBIB 4 0 2076400600007 NOCOMMON 0 0 2076400600008 DATA 4 59 2076400600009 EN EN-RSL DATA DATA-ERR 2076400600010 KEV KEV NO-DIM NO-DIM 2076400600011 1.4900E-01 4.9800E-02 1.6390E-02 1.2400E-03 2076400600012 2.4900E-01 4.9900E-02 1.0620E-02 1.2400E-03 2076400600013 3.4900E-01 4.9700E-02 2.0560E-02 1.7000E-03 2076400600014 4.4800E-01 4.9800E-02 1.2320E-02 1.5500E-03 2076400600015 5.4800E-01 4.9700E-02 9.2380E-03 1.7500E-03 2076400600016 6.9800E-01 9.9900E-02 1.2540E-02 1.2800E-03 2076400600017 8.9800E-01 1.0000E-02 1.1110E-02 1.8700E-03 2076400600018 1.0700E+00 8.1000E-02 1.7180E-02 2.3400E-03 2076400600019 1.2500E+00 9.8900E-02 1.1900E-02 1.9100E-03 2076400600020 1.4600E+00 1.0800E-01 9.8790E-03 1.9700E-03 2076400600021 1.7000E+00 1.3100E-01 7.4190E-03 1.8000E-03 2076400600022 1.9900E+00 1.5400E-01 6.2410E-03 1.7500E-03 2076400600023 2.3200E+00 1.7800E-01 1.0950E-02 2.1000E-03 2076400600024 2.7100E+00 2.0500E-01 1.1460E-02 2.2400E-03 2076400600025 3.1600E+00 2.4600E-01 1.1280E-02 2.2500E-03 2076400600026 3.6800E+00 2.7800E-01 8.6250E-03 1.9900E-03 2076400600027 4.2900E+00 3.3100E-01 9.1420E-03 2.0800E-03 2076400600028 5.0100E+00 3.8700E-01 1.1840E-02 2.4100E-03 2076400600029 5.8500E+00 4.4900E-01 1.2530E-02 2.6500E-03 2076400600030 6.8100E+00 5.1600E-01 9.7090E-03 2.2800E-03 2076400600031 7.9400E+00 6.1200E-01 1.6690E-02 2.9200E-03 2076400600032 9.2700E+00 7.1000E-01 1.1960E-02 2.5200E-03 2076400600033 1.0800E+01 8.3700E-01 1.0970E-02 2.4100E-03 2076400600034 1.2600E+01 9.5500E-01 1.4620E-02 2.8300E-03 2076400600035 1.4600E+01 1.1000E+00 1.5710E-02 3.0100E-03 2076400600036 1.7000E+01 1.3100E+00 1.1560E-02 2.6100E-03 2076400600037 1.9900E+01 1.5600E+00 1.2900E-02 2.6800E-03 2076400600038 2.3300E+01 1.7800E+00 1.3960E-02 2.6900E-03 2076400600039 2.7100E+01 2.0000E+00 1.0280E-02 2.6100E-03 2076400600040 3.1500E+01 2.4200E+00 7.3290E-03 2.0800E-03 2076400600041 3.6700E+01 2.8000E+00 1.3730E-02 2.8300E-03 2076400600042 4.2900E+01 3.3900E+00 1.0500E-02 2.3100E-03 2076400600043 5.0000E+01 3.6800E+00 1.6500E-02 3.0000E-03 2076400600044 5.8300E+01 4.6300E+00 1.6960E-02 2.9000E-03 2076400600045 6.8200E+01 5.2400E+00 1.2260E-02 2.4500E-03 2076400600046 7.9300E+01 5.7900E+00 1.5680E-02 2.9400E-03 2076400600047 9.2300E+01 7.2800E+00 1.6420E-02 2.8800E-03 2076400600048 1.0700E+02 7.9400E+00 1.2890E-02 2.7000E-03 2076400600049 1.2500E+02 1.0000E+01 1.6620E-02 2.8000E-03 2076400600050 1.4600E+02 1.0600E+01 2.1190E-02 3.2700E-03 2076400600051 1.7000E+02 1.3300E+01 2.3240E-02 3.4100E-03 2076400600052 1.9800E+02 1.5300E+01 2.2930E-02 3.3900E-03 2076400600053 2.3100E+02 1.7300E+01 2.9820E-02 4.0200E-03 2076400600054 2.6800E+02 1.9200E+01 2.6540E-02 3.8700E-03 2076400600055 3.1100E+02 2.4000E+01 3.7730E-02 4.6900E-03 2076400600056 3.6600E+02 3.0600E+01 5.1050E-02 5.2500E-03 2076400600057 4.2500E+02 2.8800E+01 7.1760E-02 7.9400E-03 2076400600058 4.9700E+02 4.2400E+01 8.8620E-02 6.8100E-03 2076400600059 5.7700E+02 3.8000E+01 1.5470E-01 1.2100E-02 2076400600060 6.7200E+02 5.7200E+01 3.5040E-01 2.3500E-02 2076400600061 7.9000E+02 6.0800E+01 6.3200E-01 4.2700E-02 2076400600062 9.1200E+02 6.0300E+01 1.0650E+00 6.9500E-02 2076400600063 1.0600E+03 9.5300E+01 1.1190E+00 6.1100E-02 2076400600064 1.2600E+03 9.7900E+01 1.4060E+00 8.4800E-02 2076400600065 1.4400E+03 9.0700E+01 1.4940E+00 1.0900E-02 2076400600066 1.6900E+03 1.5200E+02 1.4990E+00 9.7200E-02 2076400600067 1.9900E+03 1.4500E+02 1.3780E+00 1.0400E-01 2076400600068 2.3100E+03 1.8300E+02 1.6580E+00 1.5400E-01 2076400600069 2.6500E+03 1.4900E+02 1.3120E+00 1.5100E-01 2076400600070 ENDDATA 61 0 2076400600071 ENDSUBENT 70 0 2076400699999 SUBENT 20764007 20120718 22322076400700001 BIB 5 19 2076400700002 REACTION (95-AM-241(N,F),,WID) 2076400700003 ANALYSIS (AREA) Due to the relative high amount of Pu-239 in 2076400700004 the Am-241 sample only a limited number of Am-241 2076400700005 resonances could be analysed. 2076400700006 In the energy range from 1 eV to 15 eV ten Am-241 2076400700007 resonances could be identified and their fission widths2076400700008 were derived by area analysis. 2076400700009 The absolute neutron flux Was again determined from 2076400700010 the observed number of fission events between 7.8 eV 2076400700011 and 11.0 eV in the U-235 fission chamber and 2076400700012 normalizing to 240.0 b*eV 2076400700013 The fission widths were calculated from the fission 2076400700014 areas using the neutron widths and the total widths 2076400700015 given by Derrien and Lucas: Proc. of Conf. on Nuclear 2076400700016 Cross Sections and Technology, Washington, D.c., 2076400700017 March 1975, vol. II page 637 2076400700018 REL-REF (R,20415001,H.Derrien+,C,75WASH,2,637,197503) 2076400700019 STATUS (TABLE) .Taken from Tbl.5 of AKE,78. 2076400700020 HISTORY (20061018A) Data units corrected - MEV to MILLI-EV 2076400700021 ENDBIB 19 0 2076400700022 NOCOMMON 0 0 2076400700023 DATA 3 10 2076400700024 EN-RES DATA DATA-ERR 2076400700025 EV MILLI-EV MILLI-EV 2076400700026 1.2800E+00 3.7000E-01 2.0000E-02 2076400700027 2.3700E+00 1.9000E-01 3.0000E-02 2076400700028 2.6000E+00 1.5000E-01 3.0000E-02 2076400700029 3.9700E+00 1.3000E-01 3.0000E-02 2076400700030 4.9700E+00 3.5000E-01 5.0000E-02 2076400700031 5.4200E+00 6.4000E-01 3.0000E-02 2076400700032 6.1200E+00 3.4000E-01 1.1000E-01 2076400700033 9.1200E+00 1.7000E-01 3.0000E-02 2076400700034 9.8500E+00 7.5000E-01 8.0000E-02 2076400700035 1.4680E+01 2.9000E-01 4.0000E-02 2076400700036 ENDDATA 12 0 2076400700037 ENDSUBENT 36 0 2076400799999 ENDENTRY 7 0 2076499999999