ENTRY M0381 20161018 M085M038100000001 SUBENT M0381001 20161018 M085M038100100001 BIB 13 69 M038100100002 TITLE Photonuclear cross sections of U-233 using neutron M038100100003 capture gamma-rays, near threshold. M038100100004 AUTHOR (M.A.P.V.De Moraes,M.F.Cesar) M038100100005 REFERENCE (J,NC/A,106,1165,1993) M038100100006 INSTITUTE (3BZLIPE) M038100100007 FACILITY (REAC,3BZLIPE) IEA-R1 reactor. M038100100008 INC-SOURCE (MPH=(16-S-32(N,G)16-S-33)) EG = 5.43 MEV M038100100009 (MPH=(22-TI-48(N,G)22-TI-49)) EG = 6.73 MEV M038100100010 (MPH=(25-MN-55(N,G)25-MN-56)) EG = 7.23 MEV M038100100011 (MPH=(82-PB-207(N,G)82-PB-208)) EG = 7.38 MEV M038100100012 (MPH=(26-FE-56(N,G)26-FE-57)) EG = 7.64 MEV M038100100013 (MPH=(13-AL-27(N,G)13-AL-28)) EG = 7.72 MEV M038100100014 (MPH=(30-ZN-63(N,G)30-ZN-64)) EG = 7.88 MEV M038100100015 (MPH=(29-CU-64(N,G)29-CU-65)) EG = 7.91 MEV M038100100016 (MPH=(28-NI-84(N,G)28-NI-85)) EG = 9.00 MEV M038100100017 (MPH=(24-CR-52(N,G)24-CR-53)) EG = 9.72 MEV M038100100018 DETECTOR (TRD) For fission fragments the polycarbonate M038100100019 makrofoil n (BAYER AG) sheets were used, for M038100100020 neutrons a 4 pi (long-counter) consisting of 60 He-3 M038100100021 detector conventionally distributed inside a M038100100022 moderator material (polyethen) was used. M038100100023 METHOD (FISCT) M038100100024 SAMPLE (92-U-233,ENR=0.99702) The U-233 sample contained M038100100025 52.4 mg deposited in the form of (U-3)(O-8) on four M038100100026 titanum disks each with an active diameter of 40 mm M038100100027 was used: M038100100028 Masses Isotope Isotopic percentage M038100100029 (MG) A (ATOMS/%) M038100100030 13.9 233 99.702 M038100100031 13. 234 0.236 M038100100032 12.8 235 0.012 M038100100033 12.7 238 0.05 M038100100034 ANALYSIS The direct measurements of number of fission M038100100035 fragments using the scanning of the Makrofol sheets M038100100036 by means of conventional optical microscopy. M038100100037 ERR-ANALYS (ERR-T) The total errors are given. M038100100038 The error sources were: M038100100039 (ERR-1) sample atom content - 2% of systematic error. M038100100040 (ERR-2) gamma flux - 10% of the systematic uncertain- M038100100041 ty in the photopeak efficiency determination plus M038100100042 1.5 to 3% of statistical error; M038100100043 (ERR-3) photofission events - 3.1% of the systematic M038100100044 error in the calibration for fission counting plus 2 M038100100045 to 5% of the statistical uncertainty; M038100100046 (ERR-4) photoneutron events - 1% of the systematic M038100100047 error in the calibration for neutron counting plus 6 M038100100048 to 10% of the statistical uncertainty; M038100100049 The experimental errors in nu(e) and in the relative M038100100050 intensity of the gamma-ray lines were not included M038100100051 in any error analys. M038100100052 These values resulted in a overall uncertainties of M038100100053 about 15% for the final photofission cross sections, M038100100054 about 20% for the final total neutron cross secti- M038100100055 ons, and ranged from 20 to 50% for the final photo- M038100100056 neutron cross sections. M0381 1 54 M038100100057 COMMENT The photofission and photoneutron cross sections of M038100100058 U-233 have been measured by using monochromatic and M038100100059 discrete photons produced by thermal neutron capture M038100100060 gamma-rays in several targets placed at the core of M038100100061 the IAA-R1 reactor in the energy interval from 5.43 M038100100062 to 9.72 MeV. The evaluation of the total M038100100063 photoabsorption cross sections and the parameters: M038100100064 single fission barrier, relative fissionability, M038100100065 fission probability, neutron emission/fission M038100100066 competition, nuclear temperature are also presented. M038100100067 HISTORY (19960223C) M038100100068 (19960313U) M038100100069 (20161018A) Corrected by V.Varlamov: dates, SAMPLE, M038100100070 FACILITY, ERR-ANALYS, COMMON, REACTION, STATUS. M038100100071 ENDBIB 69 0 M038100100072 COMMON 1 3 M038100100073 ERR-1 M038100100074 PER-CENT M038100100075 2.0 M038100100076 ENDCOMMON 3 0 M038100100077 ENDSUBENT 76 0 M038100199999 SUBENT M0381002 20161018 M085M038100200001 BIB 4 7 M038100200002 REACTION (92-U-233(G,ABS),,SIG) M038100200003 ANALYSIS The sum SIG(g,f) + SIG(g,n). M038100200004 STATUS (DEP,M0381003) Cross section of (g,f) reaction. M038100200005 (DEP,M0381004) Cross section of (g,n) reaction. M038100200006 (TABLE) Data from Table 3. M038100200007 HISTORY (20161018A) Corrected by V.Varlamov: REACTION, M038100200008 STATUS, ERR-T. M038100200009 ENDBIB 7 0 M038100200010 NOCOMMON 0 0 M038100200011 DATA 3 9 M038100200012 EN DATA ERR-T M038100200013 MEV MB MB M038100200014 6.73 26.2 8.3 M038100200015 7.23 40.5 9.2 M038100200016 7.38 30.3 5.9 M038100200017 7.64 31.8 5.9 M038100200018 7.72 43.8 7.5 M038100200019 7.88 41.4 11.2 M038100200020 7.91 45.6 5.9 M038100200021 9. 96.5 15.8 M038100200022 9.72 158.6 40.1 M038100200023 ENDDATA 11 0 M038100200024 ENDSUBENT 23 0 M038100299999 SUBENT M0381003 20161018 M085M038100300001 BIB 3 4 M038100300002 REACTION (92-U-233(G,F),,SIG) M038100300003 STATUS (TABLE) Data from Table 3. M038100300004 HISTORY (20161018A) Corrected by V.Varlamov: REACTION, M038100300005 STATUS, ERR-T. M038100300006 ENDBIB 4 0 M038100300007 NOCOMMON 0 0 M038100300008 DATA 3 10 M038100300009 EN DATA ERR-T M038100300010 MEV MB MB M038100300011 5.43 8.3 4.1 M038100300012 6.73 14.0 2.1 M038100300013 7.23 29.8 3.8 M038100300014 7.38 20.9 2.4 M038100300015 7.64 21.8 3.2 M038100300016 7.72 26.8 3.7 M038100300017 7.88 26.1 3.7 M038100300018 7.91 29.1 4.3 M038100300019 9. 72.8 11.6 M038100300020 9.72 98.5 17.3 M038100300021 ENDDATA 12 0 M038100300022 ENDSUBENT 21 0 M038100399999 SUBENT M0381004 20161018 M085M038100400001 BIB 3 4 M038100400002 REACTION (92-U-233(G,N)92-U-232,,SIG) M038100400003 STATUS (TABLE) Data from Table 3. M038100400004 HISTORY (20161018A) Corrected by V.Varlamov: REACTION, M038100400005 STATUS, ERR-T. M038100400006 ENDBIB 4 0 M038100400007 NOCOMMON 0 0 M038100400008 DATA 3 9 M038100400009 EN DATA ERR-T M038100400010 MEV MB MB M038100400011 6.73 12.2 6.2 M038100400012 7.23 10.7 5.3 M038100400013 7.38 9.4 3.4 M038100400014 7.64 10.0 2.7 M038100400015 7.72 17.0 3.8 M038100400016 7.88 15.2 7.5 M038100400017 7.91 16.5 1.6 M038100400018 9. 23.6 4.3 M038100400019 9.72 60.1 22.8 M038100400020 ENDDATA 11 0 M038100400021 ENDSUBENT 20 0 M038100499999 SUBENT M0381005 20161018 M085M038100500001 BIB 4 5 M038100500002 REACTION (92-U-233(G,X)0-NN-1,,SIG) M038100500003 ANALYSIS The sum SIG(g,n) + nu-bar*SIG(g,f). M038100500004 STATUS (TABLE) Data from Table 3. M038100500005 HISTORY (20161018A) Corrected by V.Varlamov: REACTION, M038100500006 STATUS, ERR-T. M038100500007 ENDBIB 5 0 M038100500008 NOCOMMON 0 0 M038100500009 DATA 3 9 M038100500010 EN DATA ERR-T M038100500011 MEV MB MB M038100500012 6.73 44.9 11.0 M038100500013 7.23 82.8 14.6 M038100500014 7.38 60.5 9.3 M038100500015 7.64 64.3 10.7 M038100500016 7.72 84.0 13.1 M038100500017 7.88 81.3 16.8 M038100500018 7.91 90.2 12.5 M038100500019 9. 221.6 35.7 M038100500020 9.72 339.8 71.9 M038100500021 ENDDATA 11 0 M038100500022 ENDSUBENT 21 0 M038100599999 ENDENTRY 5 0 M038199999999