ENTRY 22479 20171108 22672247900000001 SUBENT 22479001 20171108 22672247900100001 BIB 9 40 2247900100002 TITLE Fission cross-section measurements of Am-241 between 2247900100003 0.1eV and 10 keV with lead slowing-down spectrometer 2247900100004 and at thermal energy 2247900100005 AUTHOR (S.Yamamoto, K.Kobayashi, M.Miyoshi, I.Kimura, I.Kanno,2247900100006 N.Shinohara, Y.Fujita) 2247900100007 INSTITUTE (2JPNKTO) Yamamoto, Kobayashi, Miyoshi, Kimura, 2247900100008 Kanno, Fujita 2247900100009 (2JPNJAE) Shinohara 2247900100010 REFERENCE (J,NSE,126,201,1997) Main reference 2247900100011 (C,96PRAHA,,640,1996) Data for Am-241,243 2247900100012 ((S,ISINN-2,288,1994)=(S,JINR-E3-94-419,288,1994)) 2247900100013 First publication 2247900100014 ((S,ISINN-5,316,1997)=(S,JINR-E3-97-213,316,1997)) 2247900100015 Graphs for 241Am(n,f) and 243Am(n,f) cross sections 2247900100016 (C,94GATLIN,1,242,1994) Preliminary results 2247900100017 REL-REF (I,,K.Kobayashi+,J,NIM/A,385,145,1997) Lead slowing- 2247900100018 down time spectrometer description KULS 2247900100019 DETECTOR (SIBAR) For alpha rays detection to determine actinides2247900100020 admixtures 2247900100021 (HPGE) For gamma rays to determine samples 2247900100022 composition 2247900100023 (TRD) Track detector for investigation of uniformity 2247900100024 of sample layer 2247900100025 PART-DET (N,FF) 2247900100026 SAMPLE Purified americium solution deposited on a stainless 2247900100027 steel disk 28 mm diameter. Americium radioactive area 2247900100028 is 20 mm diameter, thickness 2.2 microgram/cm2, total 2247900100029 number of Am-241 atoms is (1.734+-0.020)E+16, Purity 2247900100030 more than 99.9% 2247900100031 Uranium-235 monitor sample, highly enriched uranium 2247900100032 oxide, purity 99.91%, Electrodeposited in the same 2247900100033 way as Am-241. Thickness 41 microgram/cm2, total 2247900100034 number of U-235 atoms is (3.283+-0.036) x 10**17 2247900100035 HISTORY (20010720C) + + Compiled by S.M. 2247900100036 (20070314A) Corrections performed on N.Ohtska comments2247900100037 (20091121U) New reference added - ISINN-5,316,1997. 2247900100038 BIB correction in SAN 002, 003. 2247900100039 (20150821A) SD: type of report is changed (R,JINR-E3...2247900100040 -> S,JINR-E3...). SF8=SDT added to REACTION in Subent 22247900100041 (20171108U) SD: Ref. 96PRAHA was added. 2247900100042 ENDBIB 40 0 2247900100043 NOCOMMON 0 0 2247900100044 ENDSUBENT 43 0 2247900199999 SUBENT 22479002 20150821 22452247900200001 BIB 13 51 2247900200002 REACTION (95-AM-241(N,F),,SIG,,SDT) 2247900200003 FACILITY (LINAC,2JPNKTO) Lineal electron accelerator, electron 2247900200004 energy 31 MeV, current 0.8 amperes, 2247900200005 repetition rate 150 Hz, pulse width 22 nsec 2247900200006 INC-SOURCE (PHOTO) Pb(G,N) Reaction. lead slowing-down 2247900200007 spectrometer of the Kyoto University Research 2247900200008 Reactor Institute 2247900200009 REL-REF (I,22731001,A.Yamanaka+,J,NST,30,(9),863,199309) 2247900200010 Experimental details 2247900200011 DETECTOR (FISCH) Double ionization (Back-To-Back - BTB) 2247900200012 chamber for fission fragments detection. 40 mm diam.,2247900200013 39 mm length filled with 97% Ar and 3% N2 mixture 2247900200014 at the pressure 1 atm, voltage 400 volts 2247900200015 (BF3) Cylindrical, length 50 mm, diameter 12 mm, 2247900200016 pressure 1 atm., voltage 1100 V 2247900200017 METHOD (SLODT) Slowing-down time 2247900200018 ANALYSIS The relative fission cross section measured below 2247900200019 1 keV with BF3 counter (10B(n,alpha)7Li MONITOR) was 2247900200020 normalized to the cross section between 200 eV and 2247900200021 1 keV measured relative to 235U(n,f) 2247900200022 CORRECTION Corrections were made for setting position of Am-241 2247900200023 and U-235 deposits, for scattering of unscattered 2247900200024 neutrons, for background subtraction 2247900200025 MONITOR (92-U-235(N,F),,SIG) For energy range 0.1 eV - 10 keV 2247900200026 (5-B-10(N,A)3-LI-7,,SIG) For energy range 2247900200027 below 1 keV 2247900200028 MONIT-REF (,R.F.Rose,R,BNL-NCS-17541,1991) ENDF/B-VI 2247900200029 ERR-ANALYS (ERR-T) Total error 2247900200030 (ERR-S,0.08,6.2) Statistical error of 241Am 2247900200031 (ERR-1,0.06,1.1) Statistical error of 235U 2247900200032 (ERR-2,,1.9) Max error of assignments of fission 2247900200033 counts for 241Am 2247900200034 (ERR-3,,0.65) Max error of assignments of fission 2247900200035 counts for 235U 2247900200036 (ERR-4) Error of number of 241Am atoms 2247900200037 (ERR-5) Error of number of 235U atoms 2247900200038 (ERR-6,,0.3) Max error of correction for the setting 2247900200039 position of the 241Am and 235U deposits 2247900200040 in the BTB chamber 2247900200041 (ERR-7,,0.2) Max error for correction for scattering 2247900200042 of unscattered neutrons by the chamber 2247900200043 (ERR-8,0.2,0.4) Error for correction to background 2247900200044 subtraction 2247900200045 (MONIT1-ERR,2.,4.) Max error of 235U(n,f) cross section2247900200046 (MONIT2-ERR) Error of 10B(n,alpha)7Li cross section 2247900200047 STATUS (TABLE) K.Kobayashi, 2001-07-20/N.Ohtsuka,2007-02-10 2247900200048 Corresponds to Fig.4 of ISINN-5,316 2247900200049 HISTORY (20070314A) Data corrected according to N.Ohtsuka 2247900200050 remarks - 2/3 of data lines removed 2247900200051 (20091121U) Reference to Fig.4 ISINN-5,316 2247900200052 (20150821A) SD: SF8=SDT added to REACTION code. 2247900200053 ENDBIB 51 0 2247900200054 COMMON 3 3 2247900200055 ERR-4 ERR-5 MONIT2-ERR 2247900200056 PER-CENT PER-CENT PER-CENT 2247900200057 1.3 1.2 2. 2247900200058 ENDCOMMON 3 0 2247900200059 DATA 3 102 2247900200060 EN DATA ERR-T 2247900200061 EV B B 2247900200062 9.45625E-2 2.064892 1.59949E-1 2247900200063 1.061E-1 2.342685 1.61219E-1 2247900200064 1.19047E-1 2.504859 1.61245E-1 2247900200065 1.33573E-1 2.934832 1.78157E-1 2247900200066 1.49871E-1 3.578383 1.87687E-1 2247900200067 1.68158E-1 4.339404 1.96827E-1 2247900200068 1.88677E-1 5.263262 2.14555E-1 2247900200069 2.11699E-1 6.290259 2.50918E-1 2247900200070 2.3753E-1 7.059409 2.68822E-1 2247900200071 2.66513E-1 7.935205 2.91936E-1 2247900200072 2.99033E-1 8.226754 2.91309E-1 2247900200073 3.3552E-1 8.396488 2.86488E-1 2247900200074 3.7646E-1 8.080438 2.73846E-1 2247900200075 4.22395E-1 7.030505 2.3749E-1 2247900200076 4.73935E-1 6.014778 2.02758E-1 2247900200077 5.31764E-1 4.941163 1.66665E-1 2247900200078 5.96649E-1 4.013954 1.3543E-1 2247900200079 6.69451E-1 3.158344 1.05647E-1 2247900200080 7.51137E-1 2.686638 9.18293E-2 2247900200081 8.42789E-1 2.435576 8.49042E-2 2247900200082 9.45625E-1 3.051402 1.07165E-1 2247900200083 1.061009 3.894669 1.35067E-1 2247900200084 1.190472 4.67809 1.60225E-1 2247900200085 1.335732 4.793366 1.62064E-1 2247900200086 1.498715 3.84834 1.32075E-1 2247900200087 1.681586 2.736242 9.49202E-2 2247900200088 1.886771 1.769691 6.21515E-2 2247900200089 2.116992 1.205615 5.09372E-2 2247900200090 2.375304 8.7349E-1 4.27661E-2 2247900200091 2.665135 8.33326E-1 3.78747E-2 2247900200092 2.99033 7.68362E-1 3.26093E-2 2247900200093 3.355206 7.08144E-1 3.21923E-2 2247900200094 3.764603 7.78731E-1 3.0791E-2 2247900200095 4.223954 1.035057 3.60821E-2 2247900200096 4.739354 1.538497 5.35551E-2 2247900200097 5.317643 1.932831 6.72045E-2 2247900200098 5.966493 1.455266 5.06287E-2 2247900200099 6.694515 1.0583 3.70088E-2 2247900200100 7.51137 7.76732E-1 2.71157E-2 2247900200101 8.427896 6.57225E-1 2.31343E-2 2247900200102 9.456255 7.23744E-1 2.50922E-2 2247900200103 10.61009 7.14986E-1 2.48433E-2 2247900200104 11.90472 6.02274E-1 2.13751E-2 2247900200105 13.35732 6.12628E-1 2.11945E-2 2247900200106 14.98715 6.18027E-1 2.14517E-2 2247900200107 16.81586 5.45131E-1 1.96465E-2 2247900200108 18.86771 4.69023E-1 1.68249E-2 2247900200109 21.16992 4.07268E-1 1.51486E-2 2247900200110 23.75304 4.0331E-1 1.4867E-2 2247900200111 26.65135 4.09834E-1 1.47353E-2 2247900200112 29.9033 3.85549E-1 1.3984E-2 2247900200113 33.55206 3.94486E-1 1.38687E-2 2247900200114 37.64603 3.78273E-1 1.32222E-2 2247900200115 42.23954 3.70158E-1 1.30318E-2 2247900200116 47.39354 3.40885E-1 1.17381E-2 2247900200117 53.17643 3.34636E-1 1.19737E-2 2247900200118 59.66493 3.34265E-1 1.20187E-2 2247900200119 66.94516 3.08581E-1 1.12421E-2 2247900200120 75.1137 2.72649E-1 1.01084E-2 2247900200121 84.27896 2.59583E-1 9.92387E-3 2247900200122 94.56255 2.46499E-1 9.34234E-3 2247900200123 106.1009 2.29975E-1 8.68616E-3 2247900200124 119.0472 2.12544E-1 8.148E-3 2247900200125 133.5732 2.13114E-1 8.3303E-3 2247900200126 149.8715 1.92297E-1 7.61884E-3 2247900200127 168.1586 1.80972E-1 7.24615E-3 2247900200128 188.6771 1.67556E-1 6.68383E-3 2247900200129 211.6991 1.66804E-1 6.77478E-3 2247900200130 237.5305 1.48324E-1 6.18422E-3 2247900200131 266.5135 1.43909E-1 6.13916E-3 2247900200132 299.033 1.40545E-1 6.43138E-3 2247900200133 335.5205 1.33182E-1 6.33416E-3 2247900200134 376.46 1.24380E-1 6.29786E-3 2247900200135 422.3955 1.27822E-1 6.7209E-3 2247900200136 473.9355 1.23155E-1 6.98906E-3 2247900200137 531.764 1.14781E-1 6.65961E-3 2247900200138 596.649 1.07422E-1 6.55063E-3 2247900200139 669.4515 9.77778E-2 6.07591E-3 2247900200140 751.137 9.21786E-2 5.89113E-3 2247900200141 842.7895 8.61403E-2 5.58964E-3 2247900200142 945.6255 8.05979E-2 5.2437E-3 2247900200143 1061.01 7.4505E-02 4.9098E-03 2247900200144 1190.475 7.2620E-02 4.7977E-03 2247900200145 1335.735 6.6905E-02 4.4656E-03 2247900200146 1498.715 6.1538E-02 4.1555E-03 2247900200147 1681.585 5.2373E-02 3.603E-03 2247900200148 1886.77 4.8482E-02 3.3892E-03 2247900200149 2116.99 4.8294E-02 3.3988E-03 2247900200150 2375.305 4.1014E-02 2.953E-03 2247900200151 2665.135 3.9935E-02 2.8946E-03 2247900200152 2990.33 4.1536E-02 3.0002E-03 2247900200153 3355.205 4.2799E-02 3.0638E-03 2247900200154 3764.6 3.8229E-02 2.7838E-03 2247900200155 4223.955 3.6241E-02 2.6479E-03 2247900200156 4739.355 3.1763E-02 2.3745E-03 2247900200157 5317.64 3.2030E-02 2.3526E-03 2247900200158 5966.49 3.1011E-02 2.2739E-03 2247900200159 6694.515 3.0121E-02 2.2441E-03 2247900200160 7511.37 3.0743E-02 2.2976E-03 2247900200161 8427.895 2.6293E-02 2.0489E-03 2247900200162 9456.255 2.5007E-02 1.9735E-03 2247900200163 10610. 2.2396E-02 1.7802E-03 2247900200164 ENDDATA 104 0 2247900200165 ENDSUBENT 164 0 2247900299999 SUBENT 22479003 20091121 22192247900300001 BIB 5 9 2247900300002 REACTION (95-AM-241(N,F),,SIG,,AV) Averaged over energy 2247900300003 interval given in the data table 2247900300004 FACILITY (LINAC,2JPNKTO) 2247900300005 MISC-COL (MISC) Total error in PER-CENT 2247900300006 STATUS (DEP,22479002) 2247900300007 (TABLE) From Table III of NSE,126,(2),201,1997 2247900300008 HISTORY (20070314U) Data error for EN= 200 - 1000 eV 2247900300009 corrected 2247900300010 (20091121U) MISC-COL keyword and NSE,126.201 added 2247900300011 ENDBIB 9 0 2247900300012 NOCOMMON 0 0 2247900300013 DATA 5 6 2247900300014 EN-MIN EN-MAX DATA ERR-T MISC 2247900300015 EV EV B B PER-CENT 2247900300016 0.1 0.89 4.897 0.199 4.1 2247900300017 0.89 3.55 1.914 0.0875 4.6 2247900300018 3.55 20. 7.6360E-01 0.0317 4.2 2247900300019 20. 200. 2.5140E-01 0.0111 4.4 2247900300020 200. 1000. 1.0965E-01 0.00628 5.7 2247900300021 1000. 10000. 3.5700E-02 0.00308 8.6 2247900300022 ENDDATA 8 0 2247900300023 ENDSUBENT 22 0 2247900399999 SUBENT 22479004 20010721 00002247900400001 BIB 10 24 2247900400002 REACTION (95-AM-241(N,F),,SIG) 2247900400003 MONITOR (92-U-235(N,F),,SIG,,MXW) 2247900400004 FACILITY (REAC,2JPNKTO) Kioto University Reactor 2247900400005 INC-SOURCE (THCOL) Thermal Neutron Facility That Consists of 2247900400006 1.4 M Long Heavy Water Tank. The Leakage 2247900400007 Neutron from a Heavy Water Tank was Used As a Thermal 2247900400008 Neutron Source of a Plane Type 2247900400009 MONIT-REF (,R.F.ROSE,R,BNL-NCS-17541,1991) ENDF/B-VI 2247900400010 REL-REF (N,,K.KOBAYASHI+,J,NST,31,(1),12,199401) Description 2247900400011 Of the Thermal Neutron Facility at Kurri 2247900400012 ANALYSIS .Reaction Cross Section For Velocity V0=2200 M/Sec 2247900400013 Was Obtained from Expression Sigma(MXW-AVG)= 2247900400014 Sigma(V0)*G(TN)*Sqrt(T0/TN)/1.128 2247900400015 INC-SPECT .Thermal Neutron Spectrum with Temperature 60 Deg-C 2247900400016 Number of Epithermal Neutrons is Negligible 2247900400017 ERR-ANALYS (ERR-T) Total Error 2247900400018 (ERR-S) Max Statistical Error 2247900400019 (ERR-1) Error of Number of Americium and Uranium 2247900400020 Counts Assignments 2247900400021 (MONIT-ERR) Error of Standard Cross Section 2247900400022 (ERR-2) Error of the Deposit of 241Am and 235U 2247900400023 In the Back-To-Back Chamber 2247900400024 (ERR-3) Error of the G-Factor 2247900400025 STATUS .FROM MAIN REFERENCE 2247900400026 ENDBIB 24 0 2247900400027 COMMON 4 3 2247900400028 ERR-S ERR-1 ERR-2 ERR-3 2247900400029 PER-CENT PER-CENT PER-CENT PER-CENT 2247900400030 0.4 1.5 0.25 1.3 2247900400031 ENDCOMMON 3 0 2247900400032 DATA 5 1 2247900400033 EN DATA ERR-T MONIT MONIT-ERR 2247900400034 EV B B B PER-CENT 2247900400035 0.0253 3.15 0.097 586.2 1. 2247900400036 ENDDATA 3 0 2247900400037 ENDSUBENT 36 0 2247900499999 ENDENTRY 4 0 2247999999999