ENTRY M0406 20161222 M086M040600000001 SUBENT M0406001 20161222 M086M040600100001 BIB 13 45 M040600100002 TITLE Photofission cross sections of U-233 and Pu-239 near M040600100003 threshold induced by gamma rays from thermal neutron M040600100004 capture. M040600100005 AUTHOR (M.A.P.V.De Moraes,M.T.F.Cesar) M040600100006 REFERENCE (J,NIM/A,277,467,1989) M040600100007 INSTITUTE (3BZLUSP) M040600100008 FACILITY (REAC,3BZLIPE) M040600100009 INC-SOURCE (MPH=(16-S-32(N,G)16-S-33)) Eg = 5.43 MeV. M040600100010 (MPH=(22-TI-48(N,G)22-TI-49)) Eg = 6.73 MeV. M040600100011 (MPH=(25-MN-55(N,G)25-MN-56)) Eg = 7.23 MeV. M040600100012 (MPH=(82-PB-207(N,G)82-PB-208)) Eg = 7.38 MeV. M040600100013 (MPH=(26-FE-56(N,G)26-FE-57)) Eg = 7.64 MeV. M040600100014 (MPH=(13-AL-27(N,G)13-AL-28)) Eg = 7.72 MeV. M040600100015 (MPH=(30-ZN-63(N,G)30-ZN-64)) Eg = 7.88 MeV. M040600100016 (MPH=(29-CU-64(N,G)29-CU-65)) Eg = 7.91 MeV. M040600100017 (MPH=(28-NI-64(N,G)28-NI-65)) Eg = 9.00 MeV. M040600100018 (MPH=(24-CR-52(N,G)24-CR-53)) Eg = 9.72 MeV. M040600100019 SAMPLE The U-233 and Pu-239 samples contained 52.4 and 51.4 M040600100020 mg respectively, deposited in the form of U-3(O-8) M040600100021 and Pu(O-2) on four titanium disks, each with an M040600100022 active diameter of 40 mm. M040600100023 METHOD (EXTB) M040600100024 DETECTOR (TRD) MAKROFOL foils (8 mu). M040600100025 ANALYSIS Direct measurement of the reaction cross section. the M040600100026 MAKROFOL foils and the U-233 and Pu-239 samples were M040600100027 irradiated in the form of 'sandwiches' separately. M040600100028 After these irradiations the tracks created by the M040600100029 fission fragments in the makrofol foils were etched. M040600100030 Finally the total number of tracks was counted by an M040600100031 automatic spark counting chamber. M040600100032 ERR-ANALYS (ERR-T) Total errors are presented. M040600100033 The systematic errors were estimated: M040600100034 (ERR-1,11.,13.) for the photon flux calibrations as M040600100035 11-13%, M040600100036 (ERR-2) fission detector efficiency as 3.1%, M040600100037 (ERR-3) mass determination as 2%, M040600100038 (ERR-4,4.,5.) self-absorption in the samples as 4-5%. M040600100039 Statistical errors are about 2-5%. M040600100040 COMMENT The photofission cross sections of U-233 and Pu-239 M040600100041 have been studied by using monocromatic and discrete M040600100042 photons, in the energy interval from 5.43 to 9.72 M040600100043 MeV, produced by thermal neutron capture. M040600100044 HISTORY (19910218C) M040600100045 (20161222A) Corrected by V.Varlamov: dates, STATUS, M040600100046 ERR-ANALYS, PART-DET deleted, lowercase. M040600100047 ENDBIB 45 0 M040600100048 COMMON 2 3 M040600100049 ERR-2 ERR-3 M040600100050 PER-CENT PER-CENT M040600100051 3.1 2.0 M040600100052 ENDCOMMON 3 0 M040600100053 ENDSUBENT 52 0 M040600199999 SUBENT M0406002 20161222 M086M040600200001 BIB 3 4 M040600200002 REACTION (92-U-233(G,F),,SIG) M040600200003 STATUS (TABLE) Data from Table 3. M040600200004 HISTORY (20161222A) Corrected by V.Varlamov: STATUS, M040600200005 ERR-T. M040600200006 ENDBIB 4 0 M040600200007 NOCOMMON 0 0 M040600200008 DATA 3 10 M040600200009 EN DATA ERR-T M040600200010 MEV MB MB M040600200011 5.43 8.25 4.08 M040600200012 6.73 13.99 2.05 M040600200013 7.23 29.79 3.84 M040600200014 7.38 20.88 2.42 M040600200015 7.64 21.82 3.20 M040600200016 7.72 26.77 3.73 M040600200017 7.88 26.14 3.70 M040600200018 7.91 29.10 4.32 M040600200019 9. 72.84 11.57 M040600200020 9.72 98.48 17.28 M040600200021 ENDDATA 12 0 M040600200022 ENDSUBENT 21 0 M040600299999 SUBENT M0406003 20161222 M086M040600300001 BIB 3 4 M040600300002 REACTION (94-PU-239(G,F),,SIG) M040600300003 STATUS (TABLE) Data from Table 3. M040600300004 HISTORY (20161222A) Corrected by V.Varlamov: STATUS, M040600300005 ERR-T. M040600300006 ENDBIB 4 0 M040600300007 NOCOMMON 0 0 M040600300008 DATA 3 10 M040600300009 EN DATA ERR-T M040600300010 MEV MB MB M040600300011 5.43 8.89 4.87 M040600300012 6.73 20.80 2.12 M040600300013 7.23 26.83 6.20 M040600300014 7.38 34.52 3.99 M040600300015 7.64 37.56 5.27 M040600300016 7.72 44.22 6.19 M040600300017 7.88 42.42 7.48 M040600300018 7.91 36.20 4.85 M040600300019 9. 92.67 14.87 M040600300020 9.72 131.85 25.02 M040600300021 ENDDATA 12 0 M040600300022 ENDSUBENT 21 0 M040600399999 SUBENT M0406004 20161222 M086M040600400001 BIB 4 8 M040600400002 REACTION ((92-U-233(G,F),,SIG)/(92-U-238(G,F),,SIG)) M040600400003 RELATIVE FISSIONABILITY. M040600400004 REL-REF (R,,O.Y.Mafra+,J,NP/A,186,110,1972) Data on cross M040600400005 section of reaction U-238(g,f). M040600400006 STATUS (DEP,M0406002) M040600400007 (TABLE) Data from Table 4. M040600400008 HISTORY (20161222A) Corrected by V.Varlamov: STATUS, M040600400009 ERR-T. M040600400010 ENDBIB 8 0 M040600400011 NOCOMMON 0 0 M040600400012 DATA 3 8 M040600400013 EN DATA ERR-T M040600400014 MEV NO-DIM NO-DIM M040600400015 6.73 1.35 .30 M040600400016 7.23 4.15 1.02 M040600400017 7.38 2.05 .32 M040600400018 7.64 2.18 .99 M040600400019 7.72 2.91 .90 M040600400020 7.88 2.35 .79 M040600400021 7.91 2.03 .37 M040600400022 9. 1.97 .66 M040600400023 ENDDATA 10 0 M040600400024 ENDSUBENT 23 0 M040600499999 SUBENT M0406005 20161222 M086M040600500001 BIB 4 8 M040600500002 REACTION ((94-PU-239(G,F),,SIG)/(92-U-238(G,F),,SIG)) M040600500003 Relative fissionability. M040600500004 REL-REF (R,,O.Y.Mafra+,J,NP/A,186,110,1972) Data on cross M040600500005 section of reaction U-238(g,f). M040600500006 STATUS (DEP,M0406003) M040600500007 (TABLE) Data from Table 4. M040600500008 HISTORY (20161222A) Corrected by V.Varlamov: STATUS, M040600500009 ERR-T. M040600500010 ENDBIB 8 0 M040600500011 NOCOMMON 0 0 M040600500012 DATA 3 8 M040600500013 EN DATA ERR-T M040600500014 MEV NO-DIM NO-DIM M040600500015 6.73 2.00 .38 M040600500016 7.23 3.74 1.16 M040600500017 7.38 3.38 .53 M040600500018 7.64 3.76 1.70 M040600500019 7.72 4.81 1.51 M040600500020 7.88 3.82 1.35 M040600500021 7.91 2.53 .42 M040600500022 9. 3.32 .85 M040600500023 ENDDATA 10 0 M040600500024 ENDSUBENT 23 0 M040600599999 ENDENTRY 5 0 M040699999999