ENTRY 22044 20071123 21902204400000001 SUBENT 22044001 20071123 21902204400100001 BIB 13 68 2204400100002 REFERENCE (J,NST,24,423,198706) 2204400100003 TITLE -Measurement of fast neutron induced fission 2204400100004 cross sections of Americium-243 relative to 2204400100005 Uranium-235. 2204400100006 AUTHOR (K.Kanda,H.Imaruoka,H.Terayama,Y.Karino,N.Hirakawa) 2204400100007 INSTITUTE (2JPNTOH) 2204400100008 FACILITY (DYNAM) 4.5 MeV dynamitron accelerator. 2204400100009 INC-SOURCE (P-T) Protons on tritium-titanium target used 2204400100010 for neutrons from 1.06 to 2.88 MeV. 2204400100011 (D-D) Deuterons on a 3 cm long gas target with 2204400100012 a 2.2 micro-m thick havar entremce foil, filled 2204400100013 to a pressure of 1.6 kg/cm2 with deuterium gas, 2204400100014 was used from 4.31 to 6.83 MeV neutron energy. 2204400100015 DETECTOR (FISCH) Parallel type ionization chamber, con- 2204400100016 taining 90% Argon and 10 per cent C-H4. 2204400100017 (SOLST) Silicon surface barrier detectors were 2204400100018 used for alpha counting to make quantitative ana- 2204400100019 lyses of the fission samples. 2204400100020 SAMPLE .The fission samples were electropolated on Pt 2204400100021 plates and sintered into oxide to fix them on 2204400100022 the plates. The americium and uranium samples 2204400100023 were placed back-to-back in the fission chamber. 2204400100024 .The composition of the samples were 2204400100025 sample thickness isotope atom- number of 2204400100026 micro-g/cm2 percent atoms X e+17 2204400100027 U-235 90.3 U-234 0.03 -- 2204400100028 U-235 99.91 11.34+/-0.15 2204400100029 U-236 0.04 -- 2204400100030 U-238 0.02 -- 2204400100031 Am-243 17.8 Pu-239 0.02 -- 2204400100032 Pu-240 0.03 0.001 2204400100033 Am-241 0.02 -- 2204400100034 Am-243 99.63 2.157+/-0.018 2204400100035 cm-244 0.30 0.006 2204400100036 CORRECTION .Corrections were applied for background due to spon- 2204400100037 taneous fission and fissions by room-scattered 2204400100038 neutrons. 2204400100039 .Corrections were also applied for fission events 2204400100040 occuring under the alpha pulses, impurities in the 2204400100041 samples and neutron spectra, neutron scattering, 2204400100042 and absorption in the samples. 2204400100043 ERR-ANALYS (ERR-1) Max Error of statistics of fission counts for 2204400100044 U-235: 0.30-0.63 % 2204400100045 (ERR-2) Max error of statistics of fission counts for 2204400100046 Am-243: 0.86-1.57 % 2204400100047 extrapol. To zero pulse-height 2204400100048 (ERR-3) Max error of extrapolation to zero pulse 2204400100049 height for U-235: 0.02-0.10 % 2204400100050 (ERR-4) Max error of extrapolation to zero pulse 2204400100051 height for Am-243 : 0.55-0.60% 2204400100052 (ERR-5) Max error of self absorption for U-235 : 2204400100053 0.21-0.22 % 2204400100054 (ERR-6) Error of self absorption for Am-243: 0.04% 2204400100055 (ERR-7) Max error of number of U-235 fissionable atoms:2204400100056 1.35-1.40% 2204400100057 (ERR-8) Max error of number of Am-243 fissionable 2204400100058 atoms: 0.84-0.87% 2204400100059 (ERR-9) Max error of Am243 sample impurity: 0.00-0.01%2204400100060 (ERR-10) Max error from parasitic neutrons: 0.00-0.04%2204400100061 (ERR-11) Max error of fission cross section used for 2204400100062 calculation of correction factor: 0.00-0.12% 2204400100063 COMMENT .Correlation matrix of the different errors are given 2204400100064 in the main reference. 2204400100065 STATUS .Data taken from main reference. 2204400100066 HISTORY (19871020C) N.O. 2204400100067 (19871210E) 2204400100068 (20071123A) Date is corrected. Error structure given 2204400100069 Last checking has been done - SM 2204400100070 ENDBIB 68 0 2204400100071 COMMON 11 6 2204400100072 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2204400100073 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 2204400100074 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2204400100075 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2204400100076 0.63 1.57 0.10 0.60 0.22 0.04 2204400100077 1.40 0.87 0.01 0.04 0.12 2204400100078 ENDCOMMON 6 0 2204400100079 ENDSUBENT 78 0 2204400199999 SUBENT 22044002 20071123 21902204400200001 BIB 5 37 2204400200002 REACTION ((95-AM-243(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2204400200003 STATUS (TABLE) Data taken from Table 3 of main reference. 2204400200004 ERR-ANALYS (DATA-ERR) The principal sources of uncertainties 2204400200005 in the cross section ratio measurements were given 2204400200006 in SAN 001 2204400200007 COVARIANCE .Table 4 of main reference: 2204400200008 Correlation matrix between each measuring point 2204400200009 .... 2204400200010 Correlation matrix (%) 2204400200011 En,MeV 2204400200012 1 2 3 4 5 6 7 8 9 10 11 -->2204400200013 1 1.06 100 2204400200014 2 1.19 50 100 2204400200015 3 1.42 58 62 100 2204400200016 4 1.79 59 62 72 100 2204400200017 5 2.14 59 63 73 73 100 2204400200018 6 2.54 58 61 71 71 72 100 2204400200019 7 2.88 58 62 72 72 73 71 100 2204400200020 8 4.31 56 60 69 70 71 69 69 100 2204400200021 9 4.74 58 62 71 72 72 70 71 69 100 2204400200022 10 5.12 57 61 70 71 72 70 70 68 70 100 2204400200023 11 5.40 58 62 71 72 72 71 71 69 71 70 100 2204400200024 12 5.73 56 60 70 70 71 69 70 67 69 68 69 -->2204400200025 13 6.03 57 61 71 71 72 70 71 68 70 69 70 -->2204400200026 14 6.47 58 62 72 72 73 71 72 69 71 70 71 -->2204400200027 15 6.83 57 61 70 71 71 69 70 68 69 69 70 -->2204400200028 En,MeV 2204400200029 ---> 12 13 14 15 2204400200030 12 5.73 ---> 100 2204400200031 13 6.03 ---> 70 100 2204400200032 14 6.47 ---> 72 74 100 2204400200033 15 6.83 ---> 71 73 75 100 2204400200034 .... 2204400200035 .Numbers in the upper row of the matrix correspond to t2204400200036 neutron energies shown in the left column of the table2204400200037 HISTORY (20071123U) Last corrections have been done: 2204400200038 covariance matrix added 2204400200039 ENDBIB 37 0 2204400200040 NOCOMMON 0 0 2204400200041 DATA 4 15 2204400200042 EN EN-RSL DATA DATA-ERR 2204400200043 MEV MEV NO-DIM PER-CENT 2204400200044 1.06 2.2E-01 0.961 1.6 2204400200045 1.19 2.3E-01 1.062 1.5 2204400200046 1.42 5.6E-01 1.105 1.3 2204400200047 1.79 5.5E-01 1.071 1.3 2204400200048 2.14 4.9E-01 1.106 1.3 2204400200049 2.54 4.8E-01 1.083 1.3 2204400200050 2.88 4.5E-01 1.114 1.3 2204400200051 4.31 6.2E-01 1.202 1.4 2204400200052 4.74 5.0E-01 1.238 1.3 2204400200053 5.12 4.4E-01 1.245 1.3 2204400200054 5.40 4.0E-01 1.277 1.3 2204400200055 5.73 3.6E-01 1.320 1.4 2204400200056 6.03 3.6E-01 1.289 1.3 2204400200057 6.47 3.4E-01 1.262 1.3 2204400200058 6.83 3.4E-01 1.201 1.4 2204400200059 ENDDATA 17 0 2204400200060 ENDSUBENT 59 0 2204400299999 SUBENT 22044003 20071123 21902204400300001 BIB 5 7 2204400300002 REACTION (95-AM-243(N,F),,SIG) 2204400300003 MONITOR (92-U-235(N,F),,SIG) Values from JENDL-2. 2204400300004 ANALYSIS .Fission cross sections calculated by multiplying 2204400300005 the cross section ratios by the uranium cross 2204400300006 sections of JENDL-2 2204400300007 STATUS (TABLE) Data taken from Table 3 of main reference. 2204400300008 HISTORY (20071123U) Last corrections have been done. 2204400300009 ENDBIB 7 0 2204400300010 NOCOMMON 0 0 2204400300011 DATA 3 15 2204400300012 EN EN-RSL DATA 2204400300013 MEV MEV B 2204400300014 1.06 2.2E-01 1.178 2204400300015 1.19 2.3E-01 1.313 2204400300016 1.42 5.6E-01 1.391 2204400300017 1.79 5.5E-01 1.381 2204400300018 2.14 4.9E-01 1.437 2204400300019 2.54 4.8E-01 1.381 2204400300020 2.88 4.5E-01 1.391 2204400300021 4.31 6.2E-01 1.357 2204400300022 4.74 5.0E-01 1.364 2204400300023 5.12 4.4E-01 1.336 2204400300024 5.40 4.0E-01 1.352 2204400300025 5.73 3.6E-01 1.402 2204400300026 6.03 3.6E-01 1.452 2204400300027 6.47 3.4E-01 1.686 2204400300028 6.83 3.4E-01 1.800 2204400300029 ENDDATA 17 0 2204400300030 ENDSUBENT 29 0 2204400399999 ENDENTRY 3 0 2204499999999