ENTRY 23078 20201217 22972307800000001 SUBENT 23078001 20201217 22972307800100001 BIB 15 86 2307800100002 TITLE Cross sections for neutron-induced fission of 235U, 2307800100003 238U, 209Bi, and natPb in the energy range from 33 2307800100004 to 200 MeV measured relative to n-p scattering 2307800100005 AUTHOR (R.Nolte, M.S.Allie, F.D.Brooks, A.Buffler, 2307800100006 V.Dangendorf, J.P.Meulders, H.Schuhmacher, F.D.Smit, 2307800100007 M.Weierganz, S.Roettger) 2307800100008 INSTITUTE (2GERPTB,3SAFSCT,2BLGLVN,3SAFITH) 2307800100009 REFERENCE (J,NSE,156,197,2007) 2307800100010 (S,AIP-1175,382,2009) 2307800100011 (J,NSTS,2,311,2002) 2307800100012 Preliminary data in figs 2307800100013 (W,NOLTE,20101116)Private communication with Ralf Nolte2307800100014 REL-REF (I,,H.Schuhmacher+,J,NIM/A,421,284,1999) 2307800100015 Details of the neutron facility in Leuvain 2307800100016 (I,,R.Nolte+,J,NIM/A,476,369,2002) 2307800100017 Details of the neutron facility in Cape Town 2307800100018 (I,,V.Dangendorf+,J,NIM/A,469,205,2001) 2307800100019 Details of proton recoil telescopes 2307800100020 FACILITY (CYCLO,2BLGLVN) En=33, 45 and 60 MeV 2307800100021 (CYCLO,3SAFITH) En=100, 15 and 200 MeV 2307800100022 INC-SOURCE (P-LI7) proton on natLi (5 to 8 mm thick) 2307800100023 INC-SPECT TOF measurements were performed to characterize the 2307800100024 7Li(p,n) neutron spectra with a BC501 scintillation 2307800100025 detector. 2307800100026 Ep: Incident proton energy (MeV) 2307800100027 E0: High energy peak (MeV) 2307800100028 E1: Lower cutoff energy (MeV) 2307800100029 d: natLi target thickness (mm) 2307800100030 F0/F: Fraction of the peak neutrons 2307800100031 -------------------------------------------- 2307800100032 Ep E0 dE E1 d F0/F 2307800100033 -------------------------------------------- 2307800100034 36.4 32.7 3.8 29.0 5 0.42 2307800100035 48.5 45.3 2.9 41.0 5 0.39 2307800100036 62.9 60.0 2.3 54.5 5 0.38 2307800100037 100 97.4 1.7 91.0 5 0.45 2307800100038 150 147.6 1.2 140.0 5 0.49 2307800100039 200 197.3 1.6 185.0 8 0.69 2307800100040 ------------------------------------------ 2307800100041 DETECTOR (TELES,PROPC,PROPC) 2307800100042 Recoil proton telescopes for the peak neutron fluence 2307800100043 measurement 2307800100044 (FISCH) Parallel-plate fission ionization chambers 2307800100045 for cross-section measurements, where 10 fissionable 2307800100046 layers were deposited on five anodes in a 2307800100047 back-to-back geometry. 2307800100048 ANALYSIS Peak fluence measurement was done before or after 2307800100049 fission measurement, and they were linked by using 2307800100050 a 238U (40 mg) fission ionization chamber and a NE102 2307800100051 detector (2 mm thick). 2307800100052 CORRECTION Corrected for 2307800100053 - Neutron transport in the fission chamber 2307800100054 - Fragment loss below pulse-height threshold 2307800100055 - Dead time 2307800100056 - Distance between telescope and fission chamber 2307800100057 - Neutron absorption in air 2307800100058 - Spatial inhomogeneity of the neutron fluence 2307800100059 - Fission due to low-energy neutrons 2307800100060 ERR-ANALYS (ERR-1,0.2,0.5) Number of fissionable nuclei (0.2-0.5%)2307800100061 (ERR-2) Chamber efficiency (1.6%)2307800100062 (ERR-3,1.,5.) Number of fission events (1-5%)2307800100063 (ERR-4,2.5,3.5) Peak fluence (2.5-3.5%)2307800100064 (ERR-5) Monitor readings (2%)2307800100065 (ERR-6) Neutron transport in fiss.chamber(0.7%)2307800100066 (ERR-7) Fragment loss below threshold (0.9%)2307800100067 (ERR-8) Dead time (0.4%)2307800100068 (ERR-9) Telescope - fiss.chamber distance(0.2%)2307800100069 (ERR-10) Neutron absorption in air (0.3%)2307800100070 (ERR-11) Inhomogeneity of neutron fluence (1.3%)2307800100071 (ERR-12,1.,7.) Fiss. due to low-energy neutrons (1-7%)2307800100072 COMMENT Ralf Nolte (2020-12-19): 2307800100073 The results documented in Nucl.Sci.Eng.156(2007)197 2307800100074 is final, and supersede those in the 2002 Nuclear Data 2307800100075 conference proceedings. "published earlier [10,11]." 2307800100076 in the "Results and Conclusions" section of the 2009 2307800100077 article should read "published earlier [10].". 2307800100078 STATUS (TABLE) Table IV of Nucl.Sci.Eng.156(2007)197 2307800100079 (APRVD) Approved by Ralf Nolte 19 Nov. 2010. 2307800100080 HISTORY (20090826C) S.M. 2307800100081 (20101107A) M.M. BIB information was added. 2307800100082 Reference S,AIP-1175,,382,2010 was added. 2307800100083 Relative errors were re-calculated by dividing factor 2307800100084 =100. according to correction of units NO-DIM -> 2307800100085 PER-CENT in COMMON. 2307800100086 (20160724U) SD: AIP-1175,382,2010 -> AIP-1175,382,2009.2307800100087 (20201217A) On. Major revisions in 002-005. 006 added. 2307800100088 ENDBIB 86 0 2307800100089 COMMON 8 6 2307800100090 ERR-2 ERR-5 ERR-6 ERR-7 ERR-8 ERR-9 2307800100091 ERR-10 ERR-11 2307800100092 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2307800100093 PER-CENT PER-CENT 2307800100094 1.6 2. 0.7 0.9 0.4 0.2 2307800100095 0.3 1.3 2307800100096 ENDCOMMON 6 0 2307800100097 ENDSUBENT 96 0 2307800199999 SUBENT 23078002 20201217 22972307800200001 BIB 9 27 2307800200002 REACTION (92-U-235(N,F),,SIG) 2307800200003 MONITOR 1(92-U-238(N,F),,SIG) En=96.5 MeV 2307800200004 2(1-H-1(N,EL)1-H-1,,DA) Other neutron energy 2307800200005 MONIT-REF 1(,A.D.Carlson,C,97TRIEST,,1223,1997) 2307800200006 2(,R.Arndt,S,NEANDC-305,39,1991) 2307800200007 SAMPLE U layer (72 mm diam.) deposited on Pt anode 2307800200008 by painting technique. 2307800200009 235U: 201.6+/-0.5 mg, 444.3 ug/cm2 thick, 2307800200010 (5.1642+/-0.0013)E+20 nuclei; 2307800200011 238U: 197.9+/-0.5 mg, 436.0 ug/cm2 thick, 2307800200012 (5.0034+-0.0013)E+20 nuclei. 2307800200013 COMMENT Of compiler M.M. In two articles J,NSTS, S,AIP-1175 2307800200014 masses are given as: U-235 - 197.8+-0.6 mg, 2307800200015 U-238 - 201.6 mg - these are misprint (according to 2307800200016 given number of atoms and thickness). 2307800200017 Right masses are given in respective Subents - from 2307800200018 J,NSE. These were confirmed by R.Nolte 16.11.2010. 2307800200019 MISC-COL (MISC) Calculated energy 2307800200020 FLAG (1.) measured relative to n-p scattering, 2307800200021 measured mean neutron energy given 2307800200022 (2.) measured relative to n-p scattering, 2307800200023 calculated mean neutron energy given 2307800200024 (3.) measured relative to 238U(n,f), 2307800200025 measured mean neutron energy given 2307800200026 ERR-ANALYS (ERR-T) Total uncertainty excluding the uncertainty 2307800200027 in the n-p cross section (5%). 2307800200028 HISTORY (20201217A) On. DATA-ERR->ERR-T.235U/238U moved to 006.2307800200029 ENDBIB 27 0 2307800200030 NOCOMMON 0 0 2307800200031 DATA 6 9 2307800200032 EN EN-ERR DATA ERR-T MISC FLAG 2307800200033 MEV MEV B B MEV NO-DIM 2307800200034 32.80 0.16 2.08 0.12 32.74 1. 2307800200035 33.00 0.18 2.10 0.11 32.74 1. 2307800200036 44.91 0.24 1.97 0.14 45.27 1. 2307800200037 46.25 0.23 1.96 0.08 45.85 1. 2307800200038 59.95 1.72 0.10 59.95 2. 2307800200039 59.95 1.96 0.12 59.95 2. 2307800200040 96.5 0.8 1.93 0.21 97.68 3. 2307800200041 147.0 1.4 1.40 0.13 147.55 1. 2307800200042 199.0 2.0 1.38 0.12 198.92 1. 2307800200043 ENDDATA 11 0 2307800200044 ENDSUBENT 43 0 2307800299999 SUBENT 23078003 20201217 22972307800300001 BIB 8 13 2307800300002 REACTION (92-U-238(N,F),,SIG) 2307800300003 MONITOR (1-H-1(N,EL)1-H-1,,DA) 2307800300004 MONIT-REF (,R.Arndt,S,NEANDC-305,39,1991) 2307800300005 SAMPLE U layer (72 mm diam.) deposited on Pt anode 2307800300006 by the painting technique. 2307800300007 238U: 197.9+/-0.5 mg, 436.0 ug/cm2 thick, 2307800300008 (5.0034+/-0.0013)E+20 nuclei. 2307800300009 MISC-COL (MISC) Calculated energy 2307800300010 FLAG (1.) Measured mean neutron energy given 2307800300011 (2.) Calculated mean neutron energy given 2307800300012 ERR-ANALYS (ERR-T) Total uncertainty excluding the uncertainty 2307800300013 in the n-p cross section (5%). 2307800300014 HISTORY (20201217A) On. DATA-ERR -> ERR-T. 2307800300015 ENDBIB 13 0 2307800300016 NOCOMMON 0 0 2307800300017 DATA 6 10 2307800300018 EN EN-ERR DATA ERR-T MISC FLAG 2307800300019 MEV MEV B B MEV NO-DIM 2307800300020 33.00 0.18 1.81 0.10 32.74 1. 2307800300021 33.95 0.16 1.82 0.09 33.51 1. 2307800300022 44.91 0.24 1.75 0.11 45.27 1. 2307800300023 45.39 0.27 1.78 0.10 45.27 1. 2307800300024 46.25 0.23 1.70 0.07 45.85 1. 2307800300025 59.95 1.62 0.09 59.95 2. 2307800300026 59.95 1.78 0.10 59.95 2. 2307800300027 60.8 0.4 1.78 0.12 60.41 1. 2307800300028 147.0 1.4 1.28 0.12 147.55 1. 2307800300029 199.0 2.0 1.27 0.12 198.92 1. 2307800300030 ENDDATA 12 0 2307800300031 ENDSUBENT 30 0 2307800399999 SUBENT 23078004 20201217 22972307800400001 BIB 8 19 2307800400002 REACTION (83-BI-209(N,F),,SIG) 2307800400003 MONITOR 1(92-U-238(N,F),,SIG) En=96.5 MeV 2307800400004 2(1-H-1(N,EL)1-H-1,,DA) Other neutron energy 2307800400005 MONIT-REF 1(,A.D.Carlson,C,97TRIEST,,1223,1997) 2307800400006 2(,R.Arndt,S,NEANDC-305,39,1991) 2307800400007 SAMPLE Bi layer deposited on Al anode by vacuum evaporation. 2307800400008 209Bi: 76.13+/-0.04 mg, 387.7 ug/cm2, 2307800400009 (2.1937+-0.0011)E+20 nuclei. 2307800400010 MISC-COL (MISC) Calculated mean neutron energy 2307800400011 FLAG (1.) n-p cross section used as reference, 2307800400012 measured mean neutron energy given 2307800400013 (2.) n-p cross section used as reference, 2307800400014 calculated mean neutron energy given 2307800400015 (3.) 238U(n,f) cross section used as reference, 2307800400016 measured mean neutron energy given 2307800400017 ERR-ANALYS (ERR-T) Total uncertainty excluding the uncertainty 2307800400018 in the n-p cross section (5%). 2307800400019 HISTORY (20101108A) Units corrected B -> MB. 2307800400020 (20201217A) On. DATA-ERR -> ERR-T. 2307800400021 ENDBIB 19 0 2307800400022 NOCOMMON 0 0 2307800400023 DATA 6 6 2307800400024 EN EN-ERR DATA ERR-T MISC FLAG 2307800400025 MEV MEV MB MB MEV NO-DIM 2307800400026 33.00 0.18 0.26 0.03 32.74 1. 2307800400027 45.39 0.27 1.90 0.12 45.27 1. 2307800400028 59.95 7.0 0.7 59.95 1. 2307800400029 96.7 0.8 22.7 1.9 97.35 1. 2307800400030 147.0 1.4 48. 6. 147.55 1. 2307800400031 199.0 2.0 69. 10. 198.92 1. 2307800400032 ENDDATA 8 0 2307800400033 ENDSUBENT 32 0 2307800499999 SUBENT 23078005 20201217 22972307800500001 BIB 6 11 2307800500002 REACTION (82-PB-0(N,F),,SIG) 2307800500003 SAMPLE Pb layer deposited on Al anode by vacuum evaporation. 2307800500004 natPb: 118.81+/-0.03 mg, 605 ug/cm2, 2307800500005 (3.4530+/-0.0019)E+20 nuclei 2307800500006 MISC-COL (MISC) Calculated mean neutron energy 2307800500007 FLAG (1.) Measured mean neutron energy given 2307800500008 (2.) Calculated mean neutron energy given 2307800500009 ERR-ANALYS (ERR-T) Total uncertainty excluding the uncertainty 2307800500010 in the n-p cross section (5%). 2307800500011 HISTORY (20101108) M.M. Units corrected B -> MB. 2307800500012 (20201217A) On. DATA-ERR -> ERR-T. 2307800500013 ENDBIB 11 0 2307800500014 NOCOMMON 0 0 2307800500015 DATA 6 4 2307800500016 EN EN-ERR DATA ERR-T MISC FLAG 2307800500017 MEV MEV MB MB MEV NO-DIM 2307800500018 45.39 0.27 0.35 0.03 45.27 1. 2307800500019 59.95 1.80 0.11 59.95 2. 2307800500020 147.0 1.4 19. 3. 147.55 1. 2307800500021 199.0 2.0 31. 4. 198.92 1. 2307800500022 ENDDATA 6 0 2307800500023 ENDSUBENT 22 0 2307800599999 SUBENT 23078006 20201217 22972307800600001 BIB 6 11 2307800600002 REACTION ((92-U-235(N,F),,SIG)/(92-U-238(N,F),,SIG)) 2307800600003 MISC-COL (MISC) Calculated mean neutron energy 2307800600004 FLAG (1.) Measured mean neutron energy given 2307800600005 (2.) Calculated mean neutron energy given 2307800600006 ERR-ANALYS (DATA-ERR) Uncertainties of the fluence measurement 2307800600007 and most of the corrections cancelled 2307800600008 STATUS (DEP,23078002) 235U(n,f) cross section 2307800600009 (DEP,23078002) 238U(n,f) cross section 2307800600010 HISTORY (20101108D) M.M. Data were deleted as duplication of 2307800600011 given in Subent 002 reactions ratio - DATA 2 . 2307800600012 (20201217S) On 2307800600013 ENDBIB 11 0 2307800600014 NOCOMMON 0 0 2307800600015 DATA 6 8 2307800600016 EN EN-ERR DATA DATA-ERR MISC FLAG 2307800600017 MEV MEV NO-DIM NO-DIM MEV NO-DIM 2307800600018 33.00 0.18 1.16 0.04 32.74 1. 2307800600019 44.91 0.24 1.13 0.05 45.27 1. 2307800600020 46.25 0.23 1.15 0.04 45.85 1. 2307800600021 59.95 1.06 0.05 59.95 2. 2307800600022 59.95 1.10 0.05 59.95 2. 2307800600023 96.5 0.8 1.15 0.09 97.68 1. 2307800600024 147.0 1.4 1.09 0.10 147.55 1. 2307800600025 199.0 2.0 1.09 0.09 198.92 1. 2307800600026 ENDDATA 10 0 2307800600027 ENDSUBENT 26 0 2307800699999 ENDENTRY 6 0 2307899999999