ENTRY 41331 20140326 41634133100000001 SUBENT 41331001 20140326 41634133100100001 BIB 16 72 4133100100002 INSTITUTE (4RUSFEI) First nine authors 4133100100003 (3HUNKOS) Last author - Starichkai 4133100100004 REFERENCE (R,INDC(CCP)-315/L,1990) Main reference. 4133100100005 Numerical data and graphs. 4133100100006 (W,SIMAKOV,199903) Data are given via Internet.4133100100007 AUTHOR (S.P.Simakov, B.V.Devkin, M.G.Kobosev, V.P.Lunev, 4133100100008 A.A.Lychagin, V.A.Talalaev, N.N.Titarenko, 4133100100009 A.B.Zelenckiy, B.V.Zhuravlev, T.Starichkai) 4133100100010 TITLE Differential neutron emission and inelastic 4133100100011 cross section from Pb-208 and Bi-209 at 14.1 MeV 4133100100012 neutron energy. 4133100100013 FACILITY (VDG,4RUSFEI) Time of flight spectrometer of Institute 4133100100014 of Physics and Power Engineering, Obninsk 4133100100015 INC-SOURCE (D-T) 2.5 nsec pulsed neutrons were generated by 4133100100016 Klystron Neutron Generator KG-0.3 of IPPE . 4133100100017 Ti-T air cooled target. Deuterons of 250 keV. 4133100100018 SAMPLE -Metallic Bi-209 (natural abundance), hollow cylinder: 4133100100019 outer diameter 50mm, inner diameter 40mm, height 50mm.4133100100020 -Metallic Pb-208 (99% enrichment), ring: 4133100100021 outer diameter 45mm, inner diameter 30mm, height 50mm;4133100100022 outer diameter 76mm, inner diameter 50mm, height 10mm.4133100100023 METHOD (TOF) Neutron flight path length was: 4133100100024 -In the case of Bi-209(N,XN) experiment 2.2 m and 7.1m4133100100025 -In the case of Pb-208(N,XN) experiment 3.1 m and 7.1m4133100100026 -In the case of Pb-208(N,N'G) experiment 2.2 m. 4133100100027 (COINC) Neutrons in coincidence with 2.61 MeV gammas 4133100100028 for Pb-208(n,inl) . 4133100100029 (ASSOP) For detector efficiency measurement. 4133100100030 (ACTIV) Al foil activity was measured by beta-gamma 4133100100031 coincidence spectrometer. 4133100100032 DETECTOR (SCIN) -NE-218 liquid scintillator 10 cm in diameter 4133100100033 and 5 cm in length. For scattered neutrons. 4133100100034 (CSICR) NaI(Tl) crystal scintillator 10 cm in diameter 4133100100035 and 10 cm in length.For gammas detection. 4133100100036 (LONGC) Long counter for monitoring neutron yield from 4133100100037 target. 4133100100038 Plastic scintillator SPS-15B (2cm diameter, 2cm length4133100100039 for neutron generator pulse control as TOF monitor. 4133100100040 Neutron detector efficiency was determined by: 4133100100041 (IOCH) - Cf-252 ionization chamber, replaced the sample4133100100042 via spectrum of prompt fission neutrons; 4133100100043 (SCIN)- measurement of n-p scattering c-s by means of 4133100100044 stilbene scintillator (1 cm diameter, 4 cm length), 4133100100045 in neutron energy range above 6 MeV; 4133100100046 (SIBAR)- associated alpha particles method by silicon 4133100100047 surface barrier detector, at 14 MeV neutron energy. 4133100100048 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) Standard c-s were used for4133100100049 calculation of incident neutron flux at sample position4133100100050 MONIT-REF (,,R,STI/DOC/10-227,1983)Data Standards for Nuclear 4133100100051 Measurements. IAEA-TECDOC-227,1983 . 4133100100052 CORRECTION -Data were corrected for multiple scattering and 4133100100053 neutron flux attenuation by Monte-Carlo code SSE. 4133100100054 ERR-ANALYS (ERR-SYS) Systematic Error 6% have to be added to 4133100100055 statistical error to get total error . 4133100100056 (ERR-1) Detector efficiency error. 4133100100057 (ERR-2) Normalization error. 4133100100058 Statistical Error form 3 to 50 %. 4133100100059 STATUS (APRVD) Received from S.Simakov, 19990326 4133100100060 (COREL,41156009) Pb-208(n,inl) c-s . 4133100100061 (COREL,41156010) Pb-208(n,2n) c-s. 4133100100062 (COREL,41156011) Bi-209(n,xn) c-s. 4133100100063 COMMENT Of compiler. In Table 2 of R,INDC(CCP)-315/L,1990 4133100100064 the data in CM-system are given, they differ from 4133100100065 authors' data presented in this Entry . 4133100100066 HISTORY (19990326R) From S.Simakov. 4133100100067 (19990401C) + + Compiled at the CJD 4133100100068 (20090819U) M.M. BIB information was added. 4133100100069 Free text was corrected to be human-readable. 4133100100070 ERR-1 -> ERR-SYS. ERR-1,ERR-2 were added. 4133100100071 COMMENT was added. 4133100100072 (20100730A) Subents 002,005 were corrected. 4133100100073 (20140326A) MONIT-REF: IAEA-227 -> STI/DOC/10-227. 4133100100074 ENDBIB 72 0 4133100100075 COMMON 4 3 4133100100076 EN ERR-SYS ERR-1 ERR-2 4133100100077 MEV PER-CENT PER-CENT PER-CENT 4133100100078 1.4100E+01 6. 5. 4. 4133100100079 ENDCOMMON 3 0 4133100100080 ENDSUBENT 79 0 4133100199999 SUBENT 41331002 20100730 41504133100200001 BIB 5 7 4133100200002 REACTION (82-PB-208(N,X)0-NN-1,,DE) Neutron emission energy 4133100200003 spectrum. 4133100200004 ERR-ANALYS (ERR-S) Relative Stat. Error . 4133100200005 ANALYSIS (INTAD) Angle integrated c-s over range 30-150 degrees.4133100200006 STATUS (TABLE) From S.Simakov 199903 . 4133100200007 HISTORY (20100730A) EM was deleted from SF5 according to the 4133100200008 comment of Naohiko Otsuka (include elastic peaks). 4133100200009 ENDBIB 7 0 4133100200010 NOCOMMON 0 0 4133100200011 DATA 3 59 4133100200012 E DATA ERR-S 4133100200013 MEV MB/MEV PER-CENT 4133100200014 5.1261E-01 1.6897E+03 8.9310E+00 4133100200015 6.9373E-01 1.9714E+03 1.5630E+00 4133100200016 8.9536E-01 1.9786E+03 1.1551E+00 4133100200017 1.0956E+00 1.8528E+03 9.7702E-01 4133100200018 1.2958E+00 1.7723E+03 8.2859E-01 4133100200019 1.4967E+00 1.6584E+03 7.9781E-01 4133100200020 1.6974E+00 1.4721E+03 8.0721E-01 4133100200021 1.8981E+00 1.3589E+03 8.5553E-01 4133100200022 2.0976E+00 1.1818E+03 9.4922E-01 4133100200023 2.2986E+00 1.0561E+03 1.0496E+00 4133100200024 2.4971E+00 9.4081E+02 1.2106E+00 4133100200025 2.6946E+00 7.3616E+02 1.4476E+00 4133100200026 2.8984E+00 5.8994E+02 1.7329E+00 4133100200027 3.1012E+00 5.0461E+02 2.0384E+00 4133100200028 3.2988E+00 4.0731E+02 2.5320E+00 4133100200029 3.4981E+00 3.4251E+02 2.9510E+00 4133100200030 3.6965E+00 3.0485E+02 3.2948E+00 4133100200031 3.8984E+00 2.7642E+02 3.3849E+00 4133100200032 4.1460E+00 2.2538E+02 1.7397E+00 4133100200033 4.4448E+00 1.8300E+02 2.0981E+00 4133100200034 4.7448E+00 1.5382E+02 2.3374E+00 4133100200035 5.0482E+00 1.2295E+02 2.8689E+00 4133100200036 5.3484E+00 9.5911E+01 3.6175E+00 4133100200037 5.6520E+00 8.7238E+01 3.9760E+00 4133100200038 5.9561E+00 7.2444E+01 4.8470E+00 4133100200039 6.2538E+00 7.2209E+01 4.9180E+00 4133100200040 6.5482E+00 7.0746E+01 5.0806E+00 4133100200041 6.8439E+00 6.8488E+01 5.1229E+00 4133100200042 7.1429E+00 5.9366E+01 5.7822E+00 4133100200043 7.4436E+00 5.6899E+01 6.2745E+00 4133100200044 7.7541E+00 5.7355E+01 5.9801E+00 4133100200045 8.0536E+00 6.0857E+01 6.2210E+00 4133100200046 8.3495E+00 6.5321E+01 5.4372E+00 4133100200047 8.6503E+00 6.2681E+01 6.3101E+00 4133100200048 8.9434E+00 7.0154E+01 5.9537E+00 4133100200049 9.2394E+00 7.3654E+01 5.6444E+00 4133100200050 9.5374E+00 6.1741E+01 6.9985E+00 4133100200051 9.8430E+00 6.1284E+01 6.3129E+00 4133100200052 1.0156E+01 5.7320E+01 6.9191E+00 4133100200053 1.0453E+01 5.0304E+01 7.8666E+00 4133100200054 1.0733E+01 4.4720E+01 8.4886E+00 4133100200055 1.1024E+01 3.5740E+01 1.0072E+01 4133100200056 1.1327E+01 3.7839E+01 1.5275E+01 4133100200057 1.1643E+01 4.4050E+01 8.0347E+00 4133100200058 1.1954E+01 4.3514E+01 8.0535E+00 4133100200059 1.2258E+01 2.9296E+01 1.4263E+01 4133100200060 1.2543E+01 1.6497E+01 1.9526E+01 4133100200061 1.2839E+01 2.7684E+01 1.1848E+01 4133100200062 1.3146E+01 4.0661E+01 7.9414E+00 4133100200063 1.3441E+01 5.3189E+01 5.9951E+00 4133100200064 1.3746E+01 9.7821E+01 3.8189E+00 4133100200065 1.4051E+01 2.2891E+02 2.2109E+00 4133100200066 1.4341E+01 4.1901E+02 1.7106E+00 4133100200067 1.4653E+01 5.5824E+02 1.6914E+00 4133100200068 1.4962E+01 4.5926E+02 1.9261E+00 4133100200069 1.5241E+01 2.6575E+02 2.6266E+00 4133100200070 1.5527E+01 1.2668E+02 4.3682E+00 4133100200071 1.5822E+01 7.4334E+01 6.1812E+00 4133100200072 1.6154E+01 3.8896E+01 2.9642E+01 4133100200073 ENDDATA 61 0 4133100200074 ENDSUBENT 73 0 4133100299999 SUBENT 41331003 20100730 41504133100300001 BIB 3 8 4133100300002 REACTION (82-PB-208(N,X)0-NN-1,EM,SIG) Neutron emission cross 4133100300003 section = SIGMA(INELASTIC)+2*SIGMA(N,2N) 4133100300004 STATUS (TABLE) Table 3 of R,INDC(CCP)-315/L,199009 . 4133100300005 (DEP,41331002) 4133100300006 (SPSDD,41156008) Superseded by revised data of 411560084133100300007 ANALYSIS (INTED) Energy-angle-integrated cross-sections . 4133100300008 (INTAD) 4133100300009 Maximal energy of neutrons from n,2n reaction 6.64 MeV.4133100300010 ENDBIB 8 0 4133100300011 NOCOMMON 0 0 4133100300012 DATA 2 1 4133100300013 DATA ERR-T 4133100300014 MB MB 4133100300015 5160. 300. 4133100300016 ENDDATA 3 0 4133100300017 ENDSUBENT 16 0 4133100399999 SUBENT 41331004 20100730 41504133100400001 BIB 5 8 4133100400002 REACTION (82-PB-208(N,INL)82-PB-208,,DE) Spectrum of inelasti- 4133100400003 cally scattered neutrons 4133100400004 ANALYSIS (INTAD) Angle exp. integrated c-s over angle range 4133100400005 60-120 degrees as result of exp.geometry. 4133100400006 METHOD (COINC) 2.61 MeV gamma from the 1st level (3-) to g.s.4133100400007 was measured in coincidence with neutron. 4133100400008 ERR-ANALYS (ERR-S) Relative stat.error 4133100400009 STATUS (TABLE) From S.Simakov 199903 . 4133100400010 ENDBIB 8 0 4133100400011 NOCOMMON 0 0 4133100400012 DATA 3 23 4133100400013 E DATA ERR-S 4133100400014 MEV MB/MEV PER-CENT 4133100400015 .45860E+01 .65265E+01 .13000E+03 4133100400016 .47800E+01 .23466E+02 .43000E+02 4133100400017 .49868E+01 .33139E+02 .36986E+02 4133100400018 .52061E+01 .36454E+02 .33021E+02 4133100400019 .53611E+01 .41267E+02 .28475E+02 4133100400020 .56079E+01 .42684E+02 .26289E+02 4133100400021 .58700E+01 .38727E+02 .28305E+02 4133100400022 .60560E+01 .44560E+02 .24529E+02 4133100400023 .62508E+01 .51072E+02 .20839E+02 4133100400024 .64553E+01 .49830E+02 .20932E+02 4133100400025 .66702E+01 .49545E+02 .20737E+02 4133100400026 .68958E+01 .52457E+02 .19376E+02 4133100400027 .71332E+01 .59778E+02 .16827E+02 4133100400028 .73830E+01 .62399E+02 .16133E+02 4133100400029 .76463E+01 .63928E+02 .15973E+02 4133100400030 .79241E+01 .69085E+02 .15158E+02 4133100400031 .82173E+01 .76106E+02 .13868E+02 4133100400032 .85271E+01 .76917E+02 .13652E+02 4133100400033 .88549E+01 .73114E+02 .14334E+02 4133100400034 .92020E+01 .62381E+02 .16327E+02 4133100400035 .95701E+01 .59172E+02 .16366E+02 4133100400036 .99609E+01 .59138E+02 .15732E+02 4133100400037 .10376E+02 .59881E+02 .15007E+02 4133100400038 ENDDATA 25 0 4133100400039 ENDSUBENT 38 0 4133100499999 SUBENT 41331005 20100730 41504133100500001 BIB 5 7 4133100500002 REACTION (83-BI-209(N,X)0-NN-1,,DE) Neutron emission energy 4133100500003 spectrum. 4133100500004 ANALYSIS (INTAD) Angle integrated c-s over range 30-150 degrees.4133100500005 ERR-ANALYS (ERR-S) Relative stat. error 4133100500006 STATUS (TABLE) From S.Simakov 199903 . 4133100500007 HISTORY (20100730A) EM was deleted from SF5 according to the 4133100500008 comment of Naohiko Otsuka (include elastic peaks). 4133100500009 ENDBIB 7 0 4133100500010 NOCOMMON 0 0 4133100500011 DATA 3 73 4133100500012 E DATA ERR-S 4133100500013 MEV MB/MEV PER-CENT 4133100500014 6.0000E-01 1.8889E+03 3.7790E+00 4133100500015 8.0000E-01 1.9305E+03 3.5980E+00 4133100500016 1.0000E+00 1.8821E+03 3.5870E+00 4133100500017 1.2000E+00 1.8095E+03 3.6010E+00 4133100500018 1.4000E+00 1.7203E+03 3.6290E+00 4133100500019 1.6000E+00 1.6085E+03 3.6650E+00 4133100500020 1.8000E+00 1.4746E+03 3.6980E+00 4133100500021 2.0000E+00 1.3293E+03 3.7570E+00 4133100500022 2.2000E+00 1.1829E+03 3.8320E+00 4133100500023 2.4000E+00 1.0462E+03 3.8930E+00 4133100500024 2.6000E+00 9.1850E+02 3.8940E+00 4133100500025 2.8000E+00 7.8146E+02 4.0030E+00 4133100500026 3.0000E+00 6.5773E+02 4.1520E+00 4133100500027 3.2000E+00 5.5372E+02 4.2690E+00 4133100500028 3.4000E+00 4.6763E+02 4.3020E+00 4133100500029 3.6000E+00 3.9653E+02 4.3300E+00 4133100500030 3.8000E+00 3.2807E+02 4.3770E+00 4133100500031 4.0000E+00 2.7617E+02 4.6970E+00 4133100500032 4.2000E+00 2.3499E+02 1.9230E+00 4133100500033 4.4000E+00 1.9440E+02 2.0090E+00 4133100500034 4.6000E+00 1.7148E+02 2.3380E+00 4133100500035 4.8000E+00 1.5111E+02 2.5360E+00 4133100500036 5.0000E+00 1.3773E+02 2.5210E+00 4133100500037 5.2000E+00 1.0762E+02 2.8570E+00 4133100500038 5.4000E+00 9.7752E+01 3.1050E+00 4133100500039 5.6000E+00 9.7044E+01 3.0780E+00 4133100500040 5.8000E+00 7.6809E+01 3.2740E+00 4133100500041 6.0000E+00 6.9824E+01 3.5150E+00 4133100500042 6.2000E+00 7.3981E+01 3.5320E+00 4133100500043 6.4000E+00 5.3701E+01 4.6330E+00 4133100500044 6.6000E+00 6.0950E+01 4.2380E+00 4133100500045 6.8000E+00 5.6201E+01 4.7690E+00 4133100500046 7.0000E+00 6.4998E+01 5.1920E+00 4133100500047 7.2000E+00 6.1023E+01 5.2660E+00 4133100500048 7.4000E+00 6.1727E+01 4.7380E+00 4133100500049 7.6000E+00 7.1808E+01 5.2540E+00 4133100500050 7.8000E+00 5.4996E+01 5.5100E+00 4133100500051 8.0000E+00 6.3219E+01 4.7120E+00 4133100500052 8.2000E+00 6.6935E+01 3.9510E+00 4133100500053 8.4000E+00 7.2726E+01 4.0910E+00 4133100500054 8.6000E+00 7.5532E+01 5.9690E+00 4133100500055 8.8000E+00 7.2929E+01 5.5100E+00 4133100500056 9.0000E+00 6.5276E+01 5.3930E+00 4133100500057 9.2000E+00 6.4102E+01 4.0870E+00 4133100500058 9.4000E+00 7.0915E+01 4.4500E+00 4133100500059 9.6000E+00 7.1413E+01 4.8510E+00 4133100500060 9.8000E+00 7.1294E+01 4.4250E+00 4133100500061 1.0000E+01 6.1662E+01 4.4450E+00 4133100500062 1.0200E+01 6.3556E+01 5.0390E+00 4133100500063 1.0400E+01 4.9106E+01 5.8430E+00 4133100500064 1.0600E+01 4.0284E+01 6.5800E+00 4133100500065 1.0800E+01 4.2216E+01 6.4880E+00 4133100500066 1.1000E+01 3.7853E+01 5.3550E+00 4133100500067 1.1200E+01 4.3771E+01 8.2550E+00 4133100500068 1.1400E+01 4.8196E+01 5.2320E+00 4133100500069 1.1600E+01 4.7507E+01 4.9990E+00 4133100500070 1.1800E+01 5.8546E+01 3.6430E+00 4133100500071 1.2000E+01 4.5933E+01 5.2610E+00 4133100500072 1.2200E+01 2.4984E+01 7.8440E+00 4133100500073 1.2400E+01 2.6140E+01 7.2580E+00 4133100500074 1.2600E+01 1.8373E+01 6.9070E+00 4133100500075 1.2800E+01 1.5280E+01 9.5540E+00 4133100500076 1.3000E+01 4.0872E+01 6.7270E+00 4133100500077 1.3200E+01 7.3077E+01 5.0710E+00 4133100500078 1.3400E+01 9.6674E+01 4.0010E+00 4133100500079 1.3600E+01 1.0977E+02 3.7790E+00 4133100500080 1.3800E+01 2.1517E+02 3.3610E+00 4133100500081 1.4000E+01 3.5649E+02 4.5940E+00 4133100500082 1.4200E+01 5.3869E+02 3.7120E+00 4133100500083 1.4400E+01 6.9402E+02 3.6180E+00 4133100500084 1.4600E+01 6.7792E+02 4.2140E+00 4133100500085 1.4800E+01 4.4208E+02 7.0080E+00 4133100500086 1.5000E+01 1.7162E+02 2.3870E+00 4133100500087 ENDDATA 75 0 4133100500088 ENDSUBENT 87 0 4133100599999 SUBENT 41331006 20100730 41504133100600001 BIB 3 8 4133100600002 REACTION (83-BI-209(N,X)0-NN-1,EM,SIG) Neutron emission cross 4133100600003 section = SIGMA(INL) + 2*SIGMA(N,2N) 4133100600004 STATUS (TABLE) Table 3 of main reference. 4133100600005 (DEP,41331005) 4133100600006 (SPSDD,41156011) Superseded by revised data of 411560114133100600007 ANALYSIS (INTED) Energy-angle-integrated cross-sections . 4133100600008 (INTAD) 4133100600009 Maximal energy of neutrons from n,2n reaction 6.55 MeV.4133100600010 ENDBIB 8 0 4133100600011 NOCOMMON 0 0 4133100600012 DATA 2 1 4133100600013 DATA ERR-T 4133100600014 MB MB 4133100600015 5220. 310. 4133100600016 ENDDATA 3 0 4133100600017 ENDSUBENT 16 0 4133100699999 ENDENTRY 6 0 4133199999999