ENTRY 40287 20151216 41734028700000001 SUBENT 40287001 20151216 41734028700100001 BIB 16 40 4028700100002 INSTITUTE (4RUSFEI) 4028700100003 REFERENCE (J,SNP,19,608,1974) Eng.transl.of YF,19,(6),1190,1974 4028700100004 (J,YF,19,(6),1190,1974) 4028700100005 AUTHOR (N.S.Biryukov,B.V.Zhuravlev,N.V.Kornilov,V.I.Plyaskin, 4028700100006 A.P.Rudenko,O.A.Sal'nikov,V.I.Trykova) 4028700100007 TITLE Inelastic scattering of neutrons with initial energy 4028700100008 9.1+-0.2 MeV and the density of nuclear levels . 4028700100009 FACILITY (CYCLO,4RUSFEI) 4028700100010 INC-SOURCE (P-T) Proton-tritium . Proton energy 10.4+-0.15 MeV 4028700100011 SAMPLE .Hollow cylinders with outer diameter 5 cm, inner 4028700100012 diameter 1.5 cm, length 6 cm. Natural isotope mixture.4028700100013 METHOD (TOF) Time of flight method with resolution 2.5 nsec/m,4028700100014 flight path 2m . 4028700100015 DETECTOR (SCIN) Liquid scint. detector 4028700100016 For monitoring: two counters - all-wave and 4028700100017 scintillation counter. 4028700100018 PART-DET (N) Neutrons 4028700100019 MONITOR (1-H-1(N,EL)1-H-1,,DA) 4028700100020 Cross sections were measured relative to the (n,p) 4028700100021 scattering cross section taken from fast 4028700100022 Neutron Phys.,Marion and Fowler 1960 4028700100023 MONIT-REF (,I.B.Marion+,B,FAST N.PH.,,1960) Fast Neutron Physics,4028700100024 I.B.Marion and I.L.Fowler, New York, London, 1960. 4028700100025 CORRECTION .Corrections is introduced on multiple scattering and 4028700100026 flux absorption in sample. 4028700100027 For contribution of backgrounds. 4028700100028 COMMENT .Experimental neutron spectra were analyzed for 4028700100029 receiving of nuclear temperature and nuclear level 4028700100030 density parameter 4028700100031 STATUS (TABLE) Data from authors 4028700100032 HISTORY (19750122C) + + Compiled at the centre - CJD + + 4028700100033 (19980930U) * correction made by CJD 4028700100034 (20150208U) SD: Updated to new date formats,lower case.4028700100035 Ref. on Engl.transl. of YF added. ERR-T -> DATA-ERR. 4028700100036 (20151205A) M.M. Article was checked, BIB information 4028700100037 was updated in TITLE,METHOD,DETECTOR,CORRECTION, 4028700100038 ERR-ANALYS,STATUS. 4028700100039 DATA-ERR -> ERR-T in Subents 002,005,008,011,014,017, 4028700100040 020 . 4028700100041 EN was corrected 9.2 -> 9.1 ( as given in articles) 4028700100042 ENDBIB 40 0 4028700100043 NOCOMMON 0 0 4028700100044 ENDSUBENT 43 0 4028700199999 SUBENT 40287002 20151216 41734028700200001 BIB 4 13 4028700200002 REACTION (26-FE-0(N,INL)26-FE-0,,DA/DE) Double-differential 4028700200003 inelastic scattering cross-section 4028700200004 ERR-ANALYS (ERR-T) Total neutron spectra error consists of 4028700200005 statistical error, detector efficiency error 4028700200006 and error of determination of energy corresponding 4028700200007 to definite pulse analyzer channel 4028700200008 (ERR-1,,4.5) Error in relative detection efficiency. 4028700200009 Monitoring error < 3% . 4028700200010 STATUS (TABLE) Data from authors 4028700200011 (APRVD) Received from authors 1975-01-12 4028700200012 Data are presented on Fig.4 of SNP,19,608,1974 4028700200013 HISTORY (19980930U) Angle moved from San 001. STATUS corrected.4028700200014 Reaction code corrected 4028700200015 ENDBIB 13 0 4028700200016 COMMON 4 3 4028700200017 EN EN-ERR EN-RSL ANG 4028700200018 MEV MEV NSEC/M ADEG 4028700200019 9.1 0.2 2.5 90. 4028700200020 ENDCOMMON 3 0 4028700200021 DATA 3 49 4028700200022 E DATA ERR-T 4028700200023 MEV MB/SR/MEV MB/SR/MEV 4028700200024 5.2000E-01 3.5800E+01 4.8000E+00 4028700200025 6.0000E-01 4.1700E+01 3.1000E+00 4028700200026 7.0000E-01 3.8500E+01 3.2000E+00 4028700200027 7.9000E-01 3.7700E+01 3.0000E+00 4028700200028 9.0000E-01 4.0200E+01 2.9000E+00 4028700200029 1.0000E+00 3.9100E+01 2.8000E+00 4028700200030 1.1000E+00 3.8200E+01 2.9000E+00 4028700200031 1.2000E+00 3.9300E+01 3.0000E+00 4028700200032 1.3000E+00 4.0200E+01 2.8000E+00 4028700200033 1.4000E+00 4.0400E+01 3.1000E+00 4028700200034 1.4900E+00 3.9300E+01 2.9000E+00 4028700200035 1.5900E+00 3.7600E+01 2.8000E+00 4028700200036 1.7000E+00 3.4700E+01 2.6000E+00 4028700200037 1.8000E+00 3.2000E+01 3.0000E+00 4028700200038 1.8900E+00 2.9700E+01 2.8000E+00 4028700200039 1.9800E+00 2.7500E+01 2.6000E+00 4028700200040 2.0900E+00 2.5400E+01 2.5000E+00 4028700200041 2.2000E+00 2.3600E+01 2.4000E+00 4028700200042 2.3100E+00 2.1700E+01 2.2000E+00 4028700200043 2.4100E+00 2.0400E+01 2.9000E+00 4028700200044 2.5100E+00 1.9100E+01 2.0000E+00 4028700200045 2.6200E+00 1.7800E+01 2.6000E+00 4028700200046 2.7000E+00 1.7000E+01 2.4000E+00 4028700200047 2.7700E+00 1.6200E+01 2.5000E+00 4028700200048 2.9000E+00 1.5000E+01 1.6000E+00 4028700200049 3.0400E+00 1.4100E+01 2.2000E+00 4028700200050 3.1300E+00 1.3300E+01 2.2000E+00 4028700200051 3.2300E+00 1.2500E+01 2.0000E+00 4028700200052 3.3400E+00 1.1900E+01 2.0000E+00 4028700200053 3.4400E+00 1.1400E+01 1.9000E+00 4028700200054 3.5600E+00 1.1000E+01 1.9000E+00 4028700200055 3.6800E+00 1.0500E+01 1.7000E+00 4028700200056 3.8100E+00 9.9000E+00 1.8000E+00 4028700200057 3.9400E+00 9.2000E+00 1.7000E+00 4028700200058 4.0800E+00 7.1000E+00 1.5000E+00 4028700200059 4.2300E+00 8.8000E+00 1.6000E+00 4028700200060 4.3900E+00 8.2000E+00 1.5000E+00 4028700200061 4.5600E+00 7.4000E+00 1.4000E+00 4028700200062 4.7300E+00 5.7000E+00 1.2000E+00 4028700200063 4.9200E+00 4.6000E+00 1.1000E+00 4028700200064 5.1200E+00 4.1000E+00 1.0000E+00 4028700200065 5.3300E+00 3.3000E+00 9.0000E-01 4028700200066 5.5500E+00 4.3000E+00 1.0000E+00 4028700200067 5.7900E+00 3.3000E+00 9.0000E-01 4028700200068 6.0400E+00 3.2000E+00 9.0000E-01 4028700200069 6.3100E+00 1.2000E+00 7.0000E-01 4028700200070 6.6000E+00 3.0000E+00 8.0000E-01 4028700200071 6.9100E+00 1.6000E+00 7.0000E-01 4028700200072 7.2500E+00 1.7000E+00 7.0000E-01 4028700200073 ENDDATA 51 0 4028700200074 ENDSUBENT 73 0 4028700299999 SUBENT 40287003 20151216 41734028700300001 BIB 4 9 4028700300002 REACTION (26-FE-0(0,0),,TEM) Nuclear temperature 4028700300003 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028700300004 (ERR-1) Uncertainty associated with the choice of 4028700300005 cross-section for the inverse reaction ( used in 4028700300006 analysis) . 4028700300007 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028700300008 (DEP,40287002) Data are obtained by analyzing of 4028700300009 spectrum from Subent 4028700300010 HISTORY (19980930U) Status corrected 4028700300011 ENDBIB 9 0 4028700300012 NOCOMMON 0 0 4028700300013 DATA 3 1 4028700300014 DATA DATA-ERR ERR-1 4028700300015 MEV MEV PER-CENT 4028700300016 9.4000E-01 4.0000E-02 5. 4028700300017 ENDDATA 3 0 4028700300018 ENDSUBENT 17 0 4028700399999 SUBENT 40287004 20151216 41734028700400001 BIB 3 10 4028700400002 REACTION (26-FE-0(0,0),,LDP) 4028700400003 level density parameter. 4028700400004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028700400005 (ERR-1) Uncertainty associated with the choice of 4028700400006 cross-section for the inverse reaction ( used in 4028700400007 analysis) . 4028700400008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028700400009 (DEP,40287002) 4028700400010 Data are obtained by analyzing of spectrum from 4028700400011 Subent 40287002 4028700400012 ENDBIB 10 0 4028700400013 NOCOMMON 0 0 4028700400014 DATA 3 1 4028700400015 DATA DATA-ERR ERR-1 4028700400016 1/MEV 1/MEV PER-CENT 4028700400017 7.9100E+00 4.7000E-01 10. 4028700400018 ENDDATA 3 0 4028700400019 ENDSUBENT 18 0 4028700499999 SUBENT 40287005 20151216 41734028700500001 BIB 4 12 4028700500002 REACTION (27-CO-59(N,INL)27-CO-59,,DA/DE) 4028700500003 double diff. inelas. scat. c-s. 4028700500004 ERR-ANALYS (ERR-T) Total neutron spectra error consists of 4028700500005 statistical error, detector efficiency error 4028700500006 and error of determination of energy corresponding 4028700500007 to definite pulse analyzer channel 4028700500008 (ERR-1,,4.5) Error in relative detection efficiency. 4028700500009 Monitoring error < 3% . 4028700500010 STATUS (TABLE) data from authors 4028700500011 (APRVD) Received from authors 19750112 4028700500012 Data are presented on Fig.5 of SNP,19,608,1974 4028700500013 HISTORY (19980930U) Angle moved from San 001. Status corrected 4028700500014 ENDBIB 12 0 4028700500015 COMMON 4 3 4028700500016 EN EN-ERR EN-RSL ANG 4028700500017 MEV MEV NSEC/M ADEG 4028700500018 9.1 0.2 2.5 90. 4028700500019 ENDCOMMON 3 0 4028700500020 DATA 3 48 4028700500021 E DATA ERR-T 4028700500022 MEV MB/SR/MEV MB/SR/MEV 4028700500023 5.3000E-01 3.3700E+01 4.0000E+00 4028700500024 6.0000E-01 3.9000E+01 3.0000E+00 4028700500025 7.0000E-01 4.2800E+01 2.9000E+00 4028700500026 8.0000E-01 4.4200E+01 2.9000E+00 4028700500027 9.0000E-01 4.6900E+01 2.8000E+00 4028700500028 1.0000E+00 4.8600E+01 2.9000E+00 4028700500029 1.1000E+00 4.7500E+01 3.3000E+00 4028700500030 1.2000E+00 4.4600E+01 2.7000E+00 4028700500031 1.3100E+00 4.1800E+01 2.7000E+00 4028700500032 1.4000E+00 4.0700E+01 3.0000E+00 4028700500033 1.4900E+00 4.0200E+01 2.9000E+00 4028700500034 1.5900E+00 3.9800E+01 2.8000E+00 4028700500035 1.7100E+00 3.7900E+01 2.7000E+00 4028700500036 1.8100E+00 3.5600E+01 3.2000E+00 4028700500037 1.9000E+00 3.3400E+01 3.0000E+00 4028700500038 1.9900E+00 3.1100E+01 2.9000E+00 4028700500039 2.0900E+00 2.8800E+01 2.7000E+00 4028700500040 2.2100E+00 2.6800E+01 2.6000E+00 4028700500041 2.2900E+00 2.5400E+01 3.5000E+00 4028700500042 2.3900E+00 2.4200E+01 2.4000E+00 4028700500043 2.4900E+00 2.2900E+01 3.2000E+00 4028700500044 2.6000E+00 2.1800E+01 2.2000E+00 4028700500045 2.7100E+00 2.0700E+01 3.0000E+00 4028700500046 2.7900E+00 2.0000E+01 2.9000E+00 4028700500047 2.8700E+00 1.9300E+01 2.8000E+00 4028700500048 2.9600E+00 1.8500E+01 2.8000E+00 4028700500049 3.1000E+00 1.7200E+01 1.9000E+00 4028700500050 3.2500E+00 1.6200E+01 2.5000E+00 4028700500051 3.3500E+00 1.5300E+01 2.4000E+00 4028700500052 3.4700E+00 1.4400E+01 2.3000E+00 4028700500053 3.5800E+00 1.3300E+01 2.2000E+00 4028700500054 3.7000E+00 1.2400E+01 2.1000E+00 4028700500055 3.8300E+00 1.1600E+01 2.0000E+00 4028700500056 3.9700E+00 1.0600E+01 1.9000E+00 4028700500057 4.1100E+00 1.1200E+01 1.9000E+00 4028700500058 4.2600E+00 8.0000E+00 1.6000E+00 4028700500059 4.4200E+00 6.5000E+00 1.4000E+00 4028700500060 4.5900E+00 7.0000E+00 1.4000E+00 4028700500061 4.7700E+00 6.2000E+00 1.3000E+00 4028700500062 4.9600E+00 6.3000E+00 1.3000E+00 4028700500063 5.1600E+00 4.9000E+00 9.0000E-01 4028700500064 5.3700E+00 3.1000E+00 9.0000E-01 4028700500065 5.5900E+00 3.7000E+00 1.0000E+00 4028700500066 5.8400E+00 4.2000E+00 1.0000E+00 4028700500067 6.0900E+00 1.9000E+00 8.0000E-01 4028700500068 6.3700E+00 2.1000E+00 7.0000E-01 4028700500069 6.6600E+00 2.6000E+00 8.0000E-01 4028700500070 6.9700E+00 2.2000E+00 7.0000E-01 4028700500071 ENDDATA 50 0 4028700500072 ENDSUBENT 71 0 4028700599999 SUBENT 40287006 20151216 41734028700600001 BIB 4 11 4028700600002 REACTION (27-CO-59(0,0),,TEM) 4028700600003 nuclear temperature 4028700600004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028700600005 (ERR-1) Uncertainty associated with the choice of 4028700600006 cross-section for the inverse reaction ( used in 4028700600007 analysis) . 4028700600008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028700600009 (DEP,40287005) 4028700600010 Data are obtained by analyzing of spectrum from 4028700600011 Subent 40287005 4028700600012 HISTORY (19980930U) Status corrected 4028700600013 ENDBIB 11 0 4028700600014 NOCOMMON 0 0 4028700600015 DATA 3 1 4028700600016 DATA DATA-ERR ERR-1 4028700600017 MEV MEV PER-CENT 4028700600018 9.9000E-01 4.0000E-02 5. 4028700600019 ENDDATA 3 0 4028700600020 ENDSUBENT 19 0 4028700699999 SUBENT 40287007 20151216 41734028700700001 BIB 4 11 4028700700002 REACTION (27-CO-59(0,0),,LDP) 4028700700003 level density parameter. 4028700700004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028700700005 (ERR-1) Uncertainty associated with the choice of 4028700700006 cross-section for the inverse reaction ( used in 4028700700007 analysis) . 4028700700008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028700700009 (DEP,40287005) 4028700700010 Data are obtained by analyzing of spectrum from 4028700700011 subent 40287005 4028700700012 HISTORY (19980930U) Status corrected 4028700700013 ENDBIB 11 0 4028700700014 NOCOMMON 0 0 4028700700015 DATA 3 1 4028700700016 DATA DATA-ERR ERR-1 4028700700017 1/MEV 1/MEV PER-CENT 4028700700018 8.6000E+00 5.2000E-01 10. 4028700700019 ENDDATA 3 0 4028700700020 ENDSUBENT 19 0 4028700799999 SUBENT 40287008 20151216 41734028700800001 BIB 4 13 4028700800002 REACTION (28-NI-0(N,INL)28-NI-0,,DA/DE) 4028700800003 double diff. inelas. scat. c-s. 4028700800004 ERR-ANALYS (ERR-T) Total neutron spectra error consists of 4028700800005 statistical error, detector efficiency error 4028700800006 and error of determination of energy corresponding 4028700800007 to definite pulse analyzer channel 4028700800008 (ERR-1,,4.5) Error in relative detection efficiency. 4028700800009 Monitoring error < 3% . 4028700800010 STATUS (TABLE) Data from authors 4028700800011 (APRVD) Received from authors 19750112 4028700800012 Data are presented on Fig.5 of SNP,19,608,1974 4028700800013 HISTORY (19980930U) Angle moved from San 001. Status corrected 4028700800014 reaction code corrected 4028700800015 ENDBIB 13 0 4028700800016 COMMON 4 3 4028700800017 EN EN-ERR EN-RSL ANG 4028700800018 MEV MEV NSEC/M ADEG 4028700800019 9.1 0.2 2.5000E+00 90. 4028700800020 ENDCOMMON 3 0 4028700800021 DATA 3 50 4028700800022 E DATA ERR-T 4028700800023 MEV MB/SR/MEV MB/SR/MEV 4028700800024 5.2000E-01 2.0600E+01 2.8000E+00 4028700800025 6.0000E-01 1.9500E+01 2.0000E+00 4028700800026 7.0000E-01 2.5100E+01 1.9000E+00 4028700800027 8.0000E-01 2.9500E+01 1.9000E+00 4028700800028 9.0000E-01 2.8200E+01 1.7000E+00 4028700800029 1.0000E+00 2.6800E+01 1.9000E+00 4028700800030 1.0900E+00 2.5300E+01 1.7000E+00 4028700800031 1.2000E+00 2.3700E+01 1.5000E+00 4028700800032 1.3000E+00 2.2600E+01 1.8000E+00 4028700800033 1.4000E+00 2.2100E+01 1.5000E+00 4028700800034 1.5000E+00 2.1800E+01 1.6000E+00 4028700800035 1.6000E+00 2.1500E+01 1.6000E+00 4028700800036 1.7000E+00 2.1000E+01 1.8000E+00 4028700800037 1.8000E+00 2.0200E+01 1.4000E+00 4028700800038 1.9100E+00 1.9100E+01 1.7000E+00 4028700800039 2.0100E+00 1.8100E+01 1.6000E+00 4028700800040 2.1100E+00 1.6900E+01 1.6000E+00 4028700800041 2.1900E+00 1.6100E+01 2.1000E+00 4028700800042 2.2800E+00 1.5100E+01 1.4000E+00 4028700800043 2.4100E+00 1.3800E+01 1.4000E+00 4028700800044 2.5100E+00 1.2800E+01 1.8000E+00 4028700800045 2.5800E+00 1.2200E+01 1.8000E+00 4028700800046 2.6900E+00 1.1200E+01 1.2000E+00 4028700800047 2.8100E+00 1.0200E+01 1.6000E+00 4028700800048 2.9000E+00 9.6000E+00 1.5000E+00 4028700800049 2.9900E+00 9.1000E+00 1.5000E+00 4028700800050 3.0800E+00 8.6000E+00 1.4000E+00 4028700800051 3.1800E+00 8.1000E+00 1.4000E+00 4028700800052 3.2800E+00 7.6000E+00 1.3000E+00 4028700800053 3.3800E+00 7.2000E+00 1.2000E+00 4028700800054 3.5000E+00 6.8000E+00 1.2000E+00 4028700800055 3.6100E+00 6.5000E+00 1.2000E+00 4028700800056 3.7400E+00 6.2000E+00 1.1000E+00 4028700800057 3.8700E+00 5.7000E+00 1.1000E+00 4028700800058 4.0100E+00 5.4000E+00 1.0000E+00 4028700800059 4.1500E+00 4.7000E+00 9.0000E-01 4028700800060 4.3000E+00 4.9000E+00 9.0000E-01 4028700800061 4.4700E+00 4.4000E+00 9.0000E-01 4028700800062 4.6400E+00 4.4000E+00 8.0000E-01 4028700800063 4.8200E+00 4.0000E+00 8.0000E-01 4028700800064 5.0100E+00 3.1000E+00 7.0000E-01 4028700800065 5.2100E+00 2.8000E+00 6.0000E-01 4028700800066 5.4300E+00 3.7000E+00 7.0000E-01 4028700800067 5.6600E+00 2.6000E+00 6.0000E-01 4028700800068 5.9000E+00 1.8000E+00 5.0000E-01 4028700800069 6.1700E+00 1.9000E+00 5.0000E-01 4028700800070 6.4400E+00 2.1000E+00 5.0000E-01 4028700800071 6.7400E+00 1.5000E+00 4.0000E-01 4028700800072 7.0600E+00 1.8000E+00 5.0000E-01 4028700800073 7.4100E+00 2.4000E+00 6.0000E-01 4028700800074 ENDDATA 52 0 4028700800075 ENDSUBENT 74 0 4028700899999 SUBENT 40287009 20151216 41734028700900001 BIB 4 11 4028700900002 REACTION (28-NI-0(0,0),,TEM) 4028700900003 nuclear temperature 4028700900004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028700900005 (ERR-1) Uncertainty associated with the choice of 4028700900006 cross-section for the inverse reaction ( used in 4028700900007 analysis) . 4028700900008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028700900009 (DEP,40287008) 4028700900010 Data are obtained by analyzing of spectrum from 4028700900011 subent 40287008 4028700900012 HISTORY (19980930U) Status corrected 4028700900013 ENDBIB 11 0 4028700900014 NOCOMMON 0 0 4028700900015 DATA 3 1 4028700900016 DATA DATA-ERR ERR-1 4028700900017 MEV MEV PER-CENT 4028700900018 9.4000E-01 3.0000E-02 5. 4028700900019 ENDDATA 3 0 4028700900020 ENDSUBENT 19 0 4028700999999 SUBENT 40287010 20151216 41734028701000001 BIB 4 11 4028701000002 REACTION (28-NI-0(0,0),,LDP) 4028701000003 level density parameter. 4028701000004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028701000005 (ERR-1) Uncertainty associated with the choice of 4028701000006 cross-section for the inverse reaction ( used in 4028701000007 analysis) . 4028701000008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028701000009 (DEP,40287008) 4028701000010 Data are obtained by analyzing of spectrum from 4028701000011 subent 40287008 4028701000012 HISTORY (19980930U) Status corrected 4028701000013 ENDBIB 11 0 4028701000014 NOCOMMON 0 0 4028701000015 DATA 3 1 4028701000016 DATA DATA-ERR ERR-1 4028701000017 1/MEV 1/MEV PER-CENT 4028701000018 8.0300E+00 4.8000E-01 10. 4028701000019 ENDDATA 3 0 4028701000020 ENDSUBENT 19 0 4028701099999 SUBENT 40287011 20151216 41734028701100001 BIB 4 13 4028701100002 REACTION (29-CU-0(N,INL)29-CU-0,,DA/DE) 4028701100003 double diff. inelas. scat. c-s. 4028701100004 ERR-ANALYS (ERR-T) Total neutron spectra error consists of 4028701100005 statistical error, detector efficiency error 4028701100006 and error of determination of energy corresponding 4028701100007 to definite pulse analyzer channel 4028701100008 (ERR-1,,4.5) Error in relative detection efficiency. 4028701100009 Monitoring error < 3% . 4028701100010 STATUS (TABLE) Data from authors 4028701100011 (APRVD) Received from authors 19750112 4028701100012 Data are presented on Fig.5 of SNP,19,608,1974 4028701100013 HISTORY (19980930U) Angle moved from San 001. Status corrected 4028701100014 reaction code corrected 4028701100015 ENDBIB 13 0 4028701100016 COMMON 4 3 4028701100017 EN EN-ERR EN-RSL ANG 4028701100018 MEV MEV NSEC/M ADEG 4028701100019 9.1 0.2 2.5000E+00 90. 4028701100020 ENDCOMMON 3 0 4028701100021 DATA 3 49 4028701100022 E DATA ERR-T 4028701100023 MEV MB/SR/MEV MB/SR/MEV 4028701100024 5.2000E-01 3.1900E+01 3.7000E+00 4028701100025 6.0000E-01 3.9900E+01 2.6000E+00 4028701100026 7.0000E-01 4.3500E+01 2.7000E+00 4028701100027 7.9000E-01 4.5200E+01 2.6000E+00 4028701100028 9.0000E-01 4.7100E+01 2.5000E+00 4028701100029 1.0000E+00 4.7900E+01 2.8000E+00 4028701100030 1.0900E+00 4.6000E+01 2.6000E+00 4028701100031 1.2000E+00 4.2700E+01 2.4000E+00 4028701100032 1.3000E+00 3.9600E+01 2.8000E+00 4028701100033 1.4000E+00 3.7500E+01 2.3000E+00 4028701100034 1.5000E+00 3.5900E+01 2.5000E+00 4028701100035 1.6100E+00 3.4600E+01 2.4000E+00 4028701100036 1.7000E+00 3.3300E+01 2.8000E+00 4028701100037 1.7900E+00 3.2000E+01 2.7000E+00 4028701100038 1.9000E+00 3.0000E+01 2.1000E+00 4028701100039 2.0200E+00 2.7700E+01 2.4000E+00 4028701100040 2.1000E+00 2.6500E+01 3.3000E+00 4028701100041 2.1800E+00 2.5300E+01 2.3000E+00 4028701100042 2.3000E+00 2.3300E+01 2.2000E+00 4028701100043 2.4000E+00 2.1900E+01 2.9000E+00 4028701100044 2.5000E+00 2.0300E+01 2.0000E+00 4028701100045 2.6100E+00 1.8900E+01 2.6000E+00 4028701100046 2.6900E+00 1.8000E+01 2.5000E+00 4028701100047 2.7700E+00 1.7100E+01 2.5000E+00 4028701100048 2.8900E+00 1.5800E+01 1.6000E+00 4028701100049 3.0300E+00 1.4600E+01 2.2000E+00 4028701100050 3.1300E+00 1.3900E+01 2.1000E+00 4028701100051 3.2300E+00 1.3100E+01 2.1000E+00 4028701100052 3.3300E+00 1.2400E+01 2.0000E+00 4028701100053 3.4500E+00 1.1600E+01 1.9000E+00 4028701100054 3.5600E+00 1.0900E+01 1.8000E+00 4028701100055 3.6900E+00 1.0100E+01 1.7000E+00 4028701100056 3.8200E+00 9.1000E+00 1.6000E+00 4028701100057 3.9500E+00 8.3000E+00 1.5000E+00 4028701100058 4.1000E+00 8.0000E+00 1.5000E+00 4028701100059 4.2500E+00 6.6000E+00 1.3000E+00 4028701100060 4.4100E+00 6.5000E+00 1.3000E+00 4028701100061 4.5800E+00 5.0000E+00 1.1000E+00 4028701100062 4.7600E+00 4.5000E+00 1.0000E+00 4028701100063 4.9500E+00 3.8000E+00 9.0000E-01 4028701100064 5.1500E+00 3.0000E+00 8.0000E-01 4028701100065 5.3700E+00 3.7000E+00 8.0000E-01 4028701100066 5.6000E+00 3.0000E+00 8.0000E-01 4028701100067 5.8500E+00 2.9000E+00 8.0000E-01 4028701100068 6.1100E+00 2.1000E+00 6.0000E-01 4028701100069 6.3900E+00 3.7000E+00 8.0000E-01 4028701100070 6.6800E+00 2.6000E+00 7.0000E-01 4028701100071 7.0100E+00 2.1000E+00 6.0000E-01 4028701100072 7.3500E+00 3.3000E+00 8.0000E-01 4028701100073 ENDDATA 51 0 4028701100074 ENDSUBENT 73 0 4028701199999 SUBENT 40287012 20151216 41734028701200001 BIB 4 11 4028701200002 REACTION (29-CU-0(0,0),,TEM) 4028701200003 nuclear temperature 4028701200004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028701200005 (ERR-1) Uncertainty associated with the choice of 4028701200006 cross-section for the inverse reaction ( used in 4028701200007 analysis) . 4028701200008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028701200009 (DEP,40287011) 4028701200010 Data are obtained by analyzing of spectrum from 4028701200011 Subent 40287011 4028701200012 HISTORY (19980930U) Status corrected 4028701200013 ENDBIB 11 0 4028701200014 NOCOMMON 0 0 4028701200015 DATA 3 1 4028701200016 DATA DATA-ERR ERR-1 4028701200017 MEV MEV PER-CENT 4028701200018 9.1000E-01 3.0000E-02 5. 4028701200019 ENDDATA 3 0 4028701200020 ENDSUBENT 19 0 4028701299999 SUBENT 40287013 20151216 41734028701300001 BIB 4 11 4028701300002 REACTION (29-CU-0(0,0),,LDP) 4028701300003 level density parameter. 4028701300004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028701300005 (ERR-1) Uncertainty associated with the choice of 4028701300006 cross-section for the inverse reaction ( used in 4028701300007 analysis) . 4028701300008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028701300009 (DEP,40287011) 4028701300010 Data are obtained by analyzing of spectrum from 4028701300011 Subent 40287011 4028701300012 HISTORY (19980930U) Status corrected 4028701300013 ENDBIB 11 0 4028701300014 NOCOMMON 0 0 4028701300015 DATA 3 1 4028701300016 DATA DATA-ERR ERR-1 4028701300017 1/MEV 1/MEV PER-CENT 4028701300018 9.8900E+00 5.7000E-01 10. 4028701300019 ENDDATA 3 0 4028701300020 ENDSUBENT 19 0 4028701399999 SUBENT 40287014 20151216 41734028701400001 BIB 4 15 4028701400002 REACTION (41-NB-93(N,INL)41-NB-93,,DA/DE) 4028701400003 Double diff. inelas. scat. c-s. 4028701400004 ERR-ANALYS (ERR-T) Total neutron spectra error consists of 4028701400005 statistical error, detector efficiency error 4028701400006 and error of determination of energy corresponding 4028701400007 to definite pulse analyzer channel 4028701400008 (ERR-1,,4.5) Error in relative detection efficiency. 4028701400009 Monitoring error < 3% . 4028701400010 STATUS (TABLE) Data from authors 4028701400011 (APRVD) Received from authors 19750112 4028701400012 (SPSDD,40275002) 4028701400013 Data are presented on Fig.5 of SNP,19,608,1974 4028701400014 HISTORY (19980930U) Angle moved from SAN 001. Status corrected 4028701400015 (20151210D) M.M. Superseded by 40275002, data are the 4028701400016 same for 90 deg angle. 4028701400017 ENDBIB 15 0 4028701400018 COMMON 4 3 4028701400019 EN EN-ERR EN-RSL ANG 4028701400020 MEV MEV NSEC/M ADEG 4028701400021 9.1 0.2 2.5000E+00 90. 4028701400022 ENDCOMMON 3 0 4028701400023 DATA 3 51 4028701400024 E DATA ERR-T 4028701400025 MEV MB/SR/MEV MB/SR/MEV 4028701400026 5.0000E-01 5.5100E+01 6.0000E+00 4028701400027 6.0000E-01 5.9700E+01 4.3000E+00 4028701400028 7.0000E-01 6.4600E+01 4.1000E+00 4028701400029 8.0000E-01 7.0200E+01 4.1000E+00 4028701400030 9.0000E-01 6.7600E+01 3.9000E+00 4028701400031 1.0000E+00 6.2000E+01 4.1000E+00 4028701400032 1.1000E+00 5.4900E+01 3.7000E+00 4028701400033 1.2000E+00 4.8300E+01 3.3000E+00 4028701400034 1.3000E+00 4.4600E+01 3.9000E+00 4028701400035 1.4000E+00 4.2800E+01 3.1000E+00 4028701400036 1.5000E+00 4.1000E+01 3.3000E+00 4028701400037 1.6000E+00 3.9200E+01 3.2000E+00 4028701400038 1.7000E+00 3.7200E+01 3.7000E+00 4028701400039 1.8000E+00 3.5000E+01 2.9000E+00 4028701400040 1.9000E+00 3.2800E+01 3.3000E+00 4028701400041 2.0000E+00 3.0900E+01 3.1000E+00 4028701400042 2.1000E+00 2.8900E+01 3.0000E+00 4028701400043 2.2000E+00 2.7300E+01 4.0000E+00 4028701400044 2.3000E+00 2.5600E+01 2.7000E+00 4028701400045 2.4000E+00 2.3200E+01 2.5000E+00 4028701400046 2.5000E+00 2.1200E+01 3.4000E+00 4028701400047 2.6000E+00 2.0000E+01 3.2000E+00 4028701400048 2.7000E+00 1.8100E+01 2.1000E+00 4028701400049 2.8000E+00 1.6400E+01 2.8000E+00 4028701400050 2.9000E+00 1.5300E+01 2.7000E+00 4028701400051 3.0000E+00 1.4300E+01 2.6000E+00 4028701400052 3.1000E+00 1.3400E+01 2.5000E+00 4028701400053 3.2000E+00 1.2200E+01 2.3000E+00 4028701400054 3.3000E+00 1.1400E+01 2.2000E+00 4028701400055 3.4000E+00 1.0600E+01 2.1000E+00 4028701400056 3.5200E+00 9.8000E+00 2.0000E+00 4028701400057 3.6500E+00 8.9000E+00 1.9000E+00 4028701400058 3.7700E+00 8.2000E+00 1.9000E+00 4028701400059 3.9000E+00 7.5000E+00 1.8000E+00 4028701400060 4.0400E+00 6.9000E+00 1.7000E+00 4028701400061 4.1800E+00 5.0000E+00 1.5000E+00 4028701400062 4.3500E+00 7.9000E+00 1.7000E+00 4028701400063 4.5000E+00 4.1000E+00 1.4000E+00 4028701400064 4.6800E+00 4.2000E+00 1.3000E+00 4028701400065 4.8800E+00 3.7000E+00 1.2000E+00 4028701400066 5.0700E+00 4.6000E+00 1.3000E+00 4028701400067 5.2800E+00 3.7000E+00 1.1000E+00 4028701400068 5.5000E+00 2.9000E+00 1.0000E+00 4028701400069 5.7300E+00 2.2000E+00 9.0000E-01 4028701400070 5.9700E+00 1.7000E+00 9.0000E-01 4028701400071 6.2500E+00 2.5000E+00 8.0000E-01 4028701400072 6.5500E+00 1.7000E+00 7.0000E-01 4028701400073 6.8500E+00 1.8000E+00 7.0000E-01 4028701400074 7.1700E+00 1.0000E+00 6.0000E-01 4028701400075 7.5200E+00 1.2000E+00 6.0000E-01 4028701400076 7.8800E+00 1.3000E+00 6.0000E-01 4028701400077 ENDDATA 53 0 4028701400078 ENDSUBENT 77 0 4028701499999 SUBENT 40287015 20151216 41734028701500001 BIB 4 11 4028701500002 REACTION (41-NB-93(0,0),,TEM) 4028701500003 nuclear temperature 4028701500004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028701500005 (ERR-1) Uncertainty associated with the choice of 4028701500006 cross-section for the inverse reaction ( used in 4028701500007 analysis) . 4028701500008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028701500009 (DEP,40287014) 4028701500010 Data are obtained by analyzing of spectrum from 4028701500011 Subent 40287014 4028701500012 HISTORY (19980930U) Status corrected 4028701500013 ENDBIB 11 0 4028701500014 NOCOMMON 0 0 4028701500015 DATA 3 1 4028701500016 DATA DATA-ERR ERR-1 4028701500017 MEV MEV PER-CENT 4028701500018 7.7000E-01 3.0000E-02 5. 4028701500019 ENDDATA 3 0 4028701500020 ENDSUBENT 19 0 4028701599999 SUBENT 40287016 20151216 41734028701600001 BIB 4 11 4028701600002 REACTION (41-NB-93(0,0),,LDP) 4028701600003 level density parameter. 4028701600004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028701600005 (ERR-1) Uncertainty associated with the choice of 4028701600006 cross-section for the inverse reaction ( used in 4028701600007 analysis) . 4028701600008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028701600009 (DEP,40287014) 4028701600010 Data are obtained by analyzing of spectrum from 4028701600011 Subent 40287014 4028701600012 HISTORY (19980930U) Status corrected 4028701600013 ENDBIB 11 0 4028701600014 NOCOMMON 0 0 4028701600015 DATA 3 1 4028701600016 DATA DATA-ERR ERR-1 4028701600017 1/MEV 1/MEV PER-CENT 4028701600018 1.4730E+01 8.9000E-01 10. 4028701600019 ENDDATA 3 0 4028701600020 ENDSUBENT 19 0 4028701699999 SUBENT 40287017 20151216 41734028701700001 BIB 4 13 4028701700002 REACTION (50-SN-0(N,INL)50-SN-0,,DA/DE) 4028701700003 double diff. inelas. scat. c-s. 4028701700004 ERR-ANALYS (ERR-T) Total neutron spectra error consists of 4028701700005 statistical error, detector efficiency error 4028701700006 and error of determination of energy corresponding 4028701700007 to definite pulse analyzer channel 4028701700008 (ERR-1,,4.5) Error in relative detection efficiency. 4028701700009 Monitoring error < 3% . 4028701700010 STATUS (TABLE) Data from authors 4028701700011 (APRVD) Received from authors 1975-01-12 4028701700012 Data are presented on Fig.5 of SNP,19,608,1974 4028701700013 HISTORY (19980930U) Angle moved from San 001. Status corrected 4028701700014 reaction code corrected 4028701700015 ENDBIB 13 0 4028701700016 COMMON 4 3 4028701700017 EN EN-ERR EN-RSL ANG 4028701700018 MEV MEV NSEC/M ADEG 4028701700019 9.1 0.2 2.5000E+00 90. 4028701700020 ENDCOMMON 3 0 4028701700021 DATA 3 49 4028701700022 E DATA ERR-T 4028701700023 MEV MB/SR/MEV MB/SR/MEV 4028701700024 5.3000E-01 8.2600E+01 1.5700E+01 4028701700025 6.0000E-01 7.5000E+01 1.0400E+01 4028701700026 7.0000E-01 9.5400E+01 9.5000E+00 4028701700027 8.0000E-01 1.0030E+02 9.0000E+00 4028701700028 9.0000E-01 9.6800E+01 9.1000E+00 4028701700029 1.0000E+00 9.0000E+01 8.1000E+00 4028701700030 1.1000E+00 8.3300E+01 7.9000E+00 4028701700031 1.2000E+00 7.9300E+01 7.8000E+00 4028701700032 1.3000E+00 7.4500E+01 6.8000E+00 4028701700033 1.4000E+00 6.8000E+01 6.9000E+00 4028701700034 1.4900E+00 6.0400E+01 6.4000E+00 4028701700035 1.5900E+00 5.2100E+01 5.8000E+00 4028701700036 1.7100E+00 4.4000E+01 5.2000E+00 4028701700037 1.8100E+00 3.8300E+01 5.8000E+00 4028701700038 1.9000E+00 3.4700E+01 5.5000E+00 4028701700039 2.0000E+00 3.1800E+01 5.1000E+00 4028701700040 2.1000E+00 2.9400E+01 4.8000E+00 4028701700041 2.2200E+00 2.6900E+01 4.4000E+00 4028701700042 2.3100E+00 2.5900E+01 6.1000E+00 4028701700043 2.4000E+00 2.4300E+01 4.1000E+00 4028701700044 2.5100E+00 2.2800E+01 5.5000E+00 4028701700045 2.5800E+00 2.1700E+01 5.3000E+00 4028701700046 2.6900E+00 1.9900E+01 3.6000E+00 4028701700047 2.7900E+00 1.7900E+01 4.8000E+00 4028701700048 2.9000E+00 1.6700E+01 4.5000E+00 4028701700049 2.9900E+00 1.5600E+01 4.3000E+00 4028701700050 3.0900E+00 1.4400E+01 4.2000E+00 4028701700051 3.1900E+00 1.3000E+01 4.0000E+00 4028701700052 3.2900E+00 1.2100E+01 3.9000E+00 4028701700053 3.4000E+00 1.1300E+01 3.8000E+00 4028701700054 3.5200E+00 1.0400E+01 3.6000E+00 4028701700055 3.6400E+00 9.6000E+00 3.4000E+00 4028701700056 3.7600E+00 9.0000E+00 3.3000E+00 4028701700057 3.9000E+00 8.2000E+00 3.2000E+00 4028701700058 4.0400E+00 7.7000E+00 3.0000E+00 4028701700059 4.1900E+00 6.5000E+00 2.9000E+00 4028701700060 4.3400E+00 1.0200E+01 3.1000E+00 4028701700061 4.5100E+00 6.0000E+00 2.7000E+00 4028701700062 4.6900E+00 6.6000E+00 2.7000E+00 4028701700063 4.8700E+00 7.4000E+00 2.5000E+00 4028701700064 5.0700E+00 7.6000E+00 2.4000E+00 4028701700065 5.2800E+00 6.8000E+00 2.2000E+00 4028701700066 5.5100E+00 9.8000E+00 2.5000E+00 4028701700067 5.7500E+00 8.2000E+00 2.2000E+00 4028701700068 6.0000E+00 9.3000E+00 2.3000E+00 4028701700069 6.2700E+00 3.8000E+00 1.8000E+00 4028701700070 6.5600E+00 6.2000E+00 1.9000E+00 4028701700071 6.8800E+00 4.4000E+00 1.6000E+00 4028701700072 7.2100E+00 4.0000E+00 1.5000E+00 4028701700073 ENDDATA 51 0 4028701700074 ENDSUBENT 73 0 4028701799999 SUBENT 40287018 20151216 41734028701800001 BIB 4 11 4028701800002 REACTION (50-SN-0(0,0),,TEM) 4028701800003 nuclear temperature 4028701800004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028701800005 (ERR-1) Uncertainty associated with the choice of 4028701800006 cross-section for the inverse reaction ( used in 4028701800007 analysis) . 4028701800008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028701800009 (DEP,40287017) 4028701800010 Data are obtained by analyzing of spectrum from 4028701800011 subent 40287017 4028701800012 HISTORY (19980930U) Status corrected 4028701800013 ENDBIB 11 0 4028701800014 NOCOMMON 0 0 4028701800015 DATA 3 1 4028701800016 DATA DATA-ERR ERR-1 4028701800017 MEV MEV PER-CENT 4028701800018 6.8000E-01 3.0000E-02 5. 4028701800019 ENDDATA 3 0 4028701800020 ENDSUBENT 19 0 4028701899999 SUBENT 40287019 20151216 41734028701900001 BIB 4 11 4028701900002 REACTION (50-SN-0(0,0),,LDP) 4028701900003 level density parameter. 4028701900004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028701900005 (ERR-1) Uncertainty associated with the choice of 4028701900006 cross-section for the inverse reaction ( used in 4028701900007 analysis) . 4028701900008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028701900009 (DEP,40287017) 4028701900010 Data are obtained by analyzing of spectrum from 4028701900011 subent 40287017 4028701900012 HISTORY (19980930U) Status corrected 4028701900013 ENDBIB 11 0 4028701900014 NOCOMMON 0 0 4028701900015 DATA 3 1 4028701900016 DATA DATA-ERR ERR-1 4028701900017 1/MEV 1/MEV PER-CENT 4028701900018 1.3850E+01 9.0000E-01 10. 4028701900019 ENDDATA 3 0 4028701900020 ENDSUBENT 19 0 4028701999999 SUBENT 40287020 20151216 41734028702000001 BIB 4 12 4028702000002 REACTION (83-BI-209(N,INL)83-BI-209,,DA/DE) 4028702000003 double diff. inelas. scat. c-s. 4028702000004 ERR-ANALYS (ERR-T) Total neutron spectra error consists of 4028702000005 statistical error, detector efficiency error 4028702000006 and error of determination of energy corresponding 4028702000007 to definite pulse analyzer channel 4028702000008 (ERR-1,,4.5) Error in relative detection efficiency. 4028702000009 Monitoring error < 3% . 4028702000010 STATUS (TABLE) Data from authors 4028702000011 (APRVD) Received from authors 19750112 4028702000012 Data are presented on Fig.5 of SNP,19,608,1974 4028702000013 HISTORY (19980930U) Angle moved from san 001. Status corrected 4028702000014 ENDBIB 12 0 4028702000015 COMMON 4 3 4028702000016 EN EN-ERR EN-RSL ANG 4028702000017 MEV MEV NSEC/M ADEG 4028702000018 9.1 0.2 2.5000E+00 90. 4028702000019 ENDCOMMON 3 0 4028702000020 DATA 3 49 4028702000021 E DATA ERR-T 4028702000022 MEV MB/SR/MEV MB/SR/MEV 4028702000023 5.3000E-01 1.2790E+02 1.2900E+01 4028702000024 6.0000E-01 1.2410E+02 9.1000E+00 4028702000025 7.0000E-01 1.4800E+02 8.5000E+00 4028702000026 8.0000E-01 1.5990E+02 8.5000E+00 4028702000027 9.0000E-01 1.4770E+02 8.6000E+00 4028702000028 9.9000E-01 1.3130E+02 7.7000E+00 4028702000029 1.1000E+00 1.1730E+02 7.5000E+00 4028702000030 1.1900E+00 1.0950E+02 7.5000E+00 4028702000031 1.2900E+00 1.0410E+02 6.8000E+00 4028702000032 1.4000E+00 9.9600E+01 6.2000E+00 4028702000033 1.5100E+00 9.4400E+01 6.7000E+00 4028702000034 1.6100E+00 8.8900E+01 6.2000E+00 4028702000035 1.7000E+00 8.2700E+01 7.2000E+00 4028702000036 1.8100E+00 7.5500E+01 5.5000E+00 4028702000037 1.9200E+00 6.7900E+01 6.2000E+00 4028702000038 2.0100E+00 6.1500E+01 5.8000E+00 4028702000039 2.1200E+00 5.5300E+01 5.4000E+00 4028702000040 2.2000E+00 5.0800E+01 7.1000E+00 4028702000041 2.2900E+00 4.6200E+01 4.7000E+00 4028702000042 2.3900E+00 4.1900E+01 6.2000E+00 4028702000043 2.4900E+00 3.7700E+01 4.1000E+00 4028702000044 2.5900E+00 3.3800E+01 5.4000E+00 4028702000045 2.7100E+00 3.0400E+01 3.5000E+00 4028702000046 2.8300E+00 2.7300E+01 4.6000E+00 4028702000047 2.9100E+00 2.5600E+01 4.5000E+00 4028702000048 3.0000E+00 2.4000E+01 4.2000E+00 4028702000049 3.1000E+00 2.2600E+01 4.2000E+00 4028702000050 3.1900E+00 2.1200E+01 4.0000E+00 4028702000051 3.3000E+00 1.9800E+01 3.8000E+00 4028702000052 3.4000E+00 1.8700E+01 3.6000E+00 4028702000053 3.5200E+00 1.7500E+01 3.5000E+00 4028702000054 3.6400E+00 1.6600E+01 3.4000E+00 4028702000055 3.7600E+00 1.5800E+01 3.3000E+00 4028702000056 3.8900E+00 1.4900E+01 3.1000E+00 4028702000057 4.0300E+00 1.3600E+01 2.9000E+00 4028702000058 4.1800E+00 1.2000E+01 2.7000E+00 4028702000059 4.3300E+00 1.0400E+01 2.6000E+00 4028702000060 4.5000E+00 1.1800E+01 2.6000E+00 4028702000061 4.6700E+00 8.8000E+00 2.3000E+00 4028702000062 4.8500E+00 1.0200E+01 2.3000E+00 4028702000063 5.0400E+00 6.5000E+00 1.9000E+00 4028702000064 5.2500E+00 5.0000E+00 1.7000E+00 4028702000065 5.4700E+00 2.8000E+00 1.6000E+00 4028702000066 5.7000E+00 5.5000E+00 1.7000E+00 4028702000067 5.9500E+00 4.8000E+00 1.6000E+00 4028702000068 6.2100E+00 4.2000E+00 1.5000E+00 4028702000069 6.5000E+00 1.8000E+00 1.3000E+00 4028702000070 6.8000E+00 1.3000E+00 1.2000E+00 4028702000071 7.1200E+00 2.6000E+00 1.2000E+00 4028702000072 ENDDATA 51 0 4028702000073 ENDSUBENT 72 0 4028702099999 SUBENT 40287021 20151216 41734028702100001 BIB 4 11 4028702100002 REACTION (83-BI-209(0,0),,TEM) 4028702100003 nuclear temperature 4028702100004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028702100005 (ERR-1) Uncertainty associated with the choice of 4028702100006 cross-section for the inverse reaction ( used in 4028702100007 analysis) . 4028702100008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028702100009 (DEP,40287020)) 4028702100010 Data are obtained by analyzing of spectrum from 4028702100011 subent 40287020 4028702100012 HISTORY (19980930U) Status corrected 4028702100013 ENDBIB 11 0 4028702100014 NOCOMMON 0 0 4028702100015 DATA 3 1 4028702100016 DATA DATA-ERR ERR-1 4028702100017 MEV MEV PER-CENT 4028702100018 7.2000E-01 4.0000E-02 5. 4028702100019 ENDDATA 3 0 4028702100020 ENDSUBENT 19 0 4028702199999 SUBENT 40287022 20151216 41734028702200001 BIB 4 11 4028702200002 REACTION (83-BI-209(0,0),,LDP) 4028702200003 level density parameter. 4028702200004 ERR-ANALYS (DATA-ERR) Not explained, probably total. 4028702200005 (ERR-1) Uncertainty associated with the choice of 4028702200006 cross-section for the inverse reaction ( used in 4028702200007 analysis) . 4028702200008 STATUS (TABLE) Table I of Yad.Fiz. 19,1190,1974. 4028702200009 (DEP,40287020)) 4028702200010 Data are obtained by analyzing of spectrum from 4028702200011 subent 40287020 4028702200012 HISTORY (19980930U) Status corrected 4028702200013 ENDBIB 11 0 4028702200014 NOCOMMON 0 0 4028702200015 DATA 3 1 4028702200016 DATA DATA-ERR ERR-1 4028702200017 1/MEV 1/MEV PER-CENT 4028702200018 1.3760E+01 9.9000E-01 10. 4028702200019 ENDDATA 3 0 4028702200020 ENDSUBENT 19 0 4028702299999 ENDENTRY 22 0 4028799999999