ENTRY 30801 20090909 31413080100000001 SUBENT 30801001 20090909 31413080100100001 BIB 13 45 3080100100002 INSTITUTE (3SLKSLO) Institute of Physics, Electro-Physical 3080100100003 Research Centre of the Slovak Academy of Sciences 3080100100004 AUTHOR (S.Hlavac,P.Oblozinsky) 3080100100005 TITLE Gamma-ray production cross sections and gamma-ray 3080100100006 multiplicities from Fe and Ni bombarded with 3080100100007 14.6 MeV neutrons 3080100100008 REFERENCE (R,INDC(CSR)-5,198311) Summary, final data 3080100100009 FACILITY (CCW,3SLKSLO) 3080100100010 INC-SOURCE (D-T) 120keV/100mu-A separated D+ beam 3080100100011 SAMPLE Natural Fe (232 g hollow cylinder and 189 g in planar 3080100100012 form), natural Ni(150 g in planar form) and 3080100100013 Ni-58(enriched to 99%, 90 g in cylinder form) 3080100100014 METHOD (GSPEC) Discrete gamma-ray cross sections obtained from3080100100015 Ge(Li) spectra. 3080100100016 Continuous gamma-ray spectrum (for Fe only) 3080100100017 obtained from two parametric spectrum energy x time of 3080100100018 NaI(Tl) detector. Events due to neutron registered in 3080100100019 the detector as well as due to time uncorrelated 3080100100020 background events were substracted. 3080100100021 Average gamma-ray multiplicities obtained by comparing 3080100100022 Ge(Li) spectrum measured in coincidence with NaI(Tl) 3080100100023 to the Ge(Li) singles spectrum. 3080100100024 (TOF) Time-of-flight based discrimination of neutrons 3080100100025 Average gamma-ray multiplicities for cascades following3080100100026 emission of neutrons obtained from the ratio of neutron3080100100027 TOF spectrum measured in coincidence with the NaI(Tl) 3080100100028 to the TOF singles spectrum 3080100100029 DETECTOR (GELI) 70 cm3 3080100100030 (NAICR) 16 cm diam. x 10 cm 3080100100031 (SCIN) NE-213 12 cm diam.X 4 cm 3080100100032 MONITOR Stilbene detector as neutron monitor. 3080100100033 Neutrons are collimated by time correlated associated 3080100100034 alpha particles 3080100100035 PART-DET (G) 3080100100036 (N) 3080100100037 STATUS (APRVD) Approved by Hlavac and Oblozinsky 19/04/85 3080100100038 work performed under IAEA interregional project 3080100100039 INT/1/018 (INT(83)-7). 3080100100040 HISTORY (19840309C) DG.- 3080100100041 (19850425A) DG.-Corrections after author approval.- 3080100100042 (20090725A) SD:Updated to new date formats,lower case. 3080100100043 Subents 004,007 are deleted. Unclear definition of: 3080100100044 "...passing through a specific transition" 3080100100045 Subents 002,006 were splited in several Subents 3080100100046 according to modified REACTION code. 3080100100047 ENDBIB 45 0 3080100100048 COMMON 2 3 3080100100049 EN EN-RSL-FW 3080100100050 MEV MEV 3080100100051 1.4600E+01 2.0000E-01 3080100100052 ENDCOMMON 3 0 3080100100053 ENDSUBENT 52 0 3080100199999 SUBENT 30801002 20090909 31413080100200001 BIB 5 20 3080100200002 REACTION (26-FE-56(N,2N)26-FE-55,PAR,DA,G) 3080100200003 Production cross section for discrete gamma-ray 3080100200004 measured at 90 deg. 3080100200005 COMMENT Angle integrated production cross section for 847 keV 3080100200006 transition inferred from 90-deg.value and ang.distrib. 3080100200007 of ref.(Degtyarev+,Ukr.Fiz.Zh.22(1977)1463) is 3080100200008 560 +- 70 mb. 3080100200009 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 1. 3080100200010 ERR-ANALYS (DATA-ERR) Over all 7. - 12. % 3080100200011 Following uncertainties are included: 3080100200012 Source of error Value(in %) 3080100200013 (ERR-1) No.of atoms in the sample 0.15 3080100200014 (ERR-2) Neutron flux 4. 3080100200015 (ERR-3,0.5,10.) Area of full energy peak (FEP) 0.5 - 103080100200016 (ERR-4) Efficiency in FEP 5. 3080100200017 (ERR-5) Corrections 3. 3080100200018 HISTORY (20090909A) SD: Cosmetic changes, codes for partial 3080100200019 uncertainties and data to COMMON section are added. 3080100200020 Subent 002 was splited in several Subents 3080100200021 according to modified REACTION code. 3080100200022 ENDBIB 20 0 3080100200023 COMMON 5 3 3080100200024 ANG ERR-1 ERR-2 ERR-4 ERR-5 3080100200025 ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3080100200026 9.0000E+01 0.15 4. 5. 3. 3080100200027 ENDCOMMON 3 0 3080100200028 DATA 3 7 3080100200029 E DATA DATA-ERR 3080100200030 KEV MB/SR MB/SR 3080100200031 4.1200E+02 2.0400E+00 2.9000E-01 3080100200032 4.7800E+02 2.2400E+00 3.4000E-01 3080100200033 8.0300E+02 6.7000E-01 1.1000E-01 3080100200034 9.3100E+02 7.0600E+00 9.4000E-01 3080100200035 1.3170E+03 3.1000E-01 5.0000E-02 3080100200036 1.3690E+03 4.7000E-01 1.3000E-01 3080100200037 1.4090E+03 2.3100E+00 3.7000E-01 3080100200038 ENDDATA 9 0 3080100200039 ENDSUBENT 38 0 3080100299999 SUBENT 30801003 20090909 31413080100300001 BIB 5 9 3080100300002 REFERENCE (C,80KIEV,1,210,198009) Graph only 3080100300003 (S,ZFK-459,153,198109) Graph only 3080100300004 REACTION (26-FE-0(N,X)0-G-0,,DA/DE) 3080100300005 Continuous gamma-ray spectrum at 90-deg. 3080100300006 COMMENT 90-deg. Total gamma ray yield (above 0.2 MeV) is 3080100300007 256 +- 16 mb/sr. 3080100300008 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 3. 3080100300009 ERR-ANALYS (DATA-ERR) Errors do not include a contribution 3080100300010 due to the unfolding procedure. 3080100300011 ENDBIB 9 0 3080100300012 COMMON 1 3 3080100300013 ANG 3080100300014 ADEG 3080100300015 9.0000E+01 3080100300016 ENDCOMMON 3 0 3080100300017 DATA 3 124 3080100300018 E DATA DATA-ERR 3080100300019 MEV B/SR/MEV B/SR/MEV 3080100300020 2.0000E-01 8.8500E-02 6.3000E-03 3080100300021 3.0000E-01 8.2200E-02 5.8000E-03 3080100300022 4.0000E-01 1.0500E-01 8.0000E-03 3080100300023 5.0000E-01 1.4000E-01 1.0000E-02 3080100300024 6.0000E-01 3.5800E-02 2.5000E-03 3080100300025 7.0000E-01 2.9100E-02 2.1000E-03 3080100300026 8.0000E-01 2.6900E-01 1.9000E-02 3080100300027 9.0000E-01 2.3600E-01 1.7000E-02 3080100300028 1.0000E+00 5.0300E-02 3.6000E-03 3080100300029 1.1000E+00 4.4300E-02 3.1000E-03 3080100300030 1.2000E+00 1.6500E-01 1.2000E-02 3080100300031 1.3000E+00 1.7100E-01 1.2000E-02 3080100300032 1.4000E+00 4.4600E-02 3.2000E-03 3080100300033 1.5000E+00 2.5300E-02 1.8000E-03 3080100300034 1.6000E+00 3.2800E-02 2.3000E-03 3080100300035 1.7000E+00 4.2800E-02 3.0000E-03 3080100300036 1.8000E+00 4.9300E-02 3.5000E-03 3080100300037 1.9000E+00 2.7600E-02 2.0000E-03 3080100300038 2.0000E+00 2.0800E-02 1.5000E-03 3080100300039 2.1000E+00 2.7100E-02 1.9000E-03 3080100300040 2.2000E+00 2.0200E-02 1.4000E-03 3080100300041 2.3000E+00 2.1100E-02 1.5000E-03 3080100300042 2.4000E+00 1.2200E-02 9.0000E-04 3080100300043 2.5000E+00 3.1700E-02 2.3000E-03 3080100300044 2.6000E+00 2.5600E-02 1.9000E-03 3080100300045 2.7000E+00 2.2400E-02 1.6000E-03 3080100300046 2.8000E+00 1.4500E-02 1.1000E-03 3080100300047 2.9000E+00 1.5900E-02 1.2000E-03 3080100300048 3.0000E+00 1.5600E-02 1.2000E-03 3080100300049 3.1000E+00 1.3700E-02 1.1000E-03 3080100300050 3.2000E+00 1.7400E-02 1.3000E-03 3080100300051 3.3000E+00 2.1800E-02 1.6000E-03 3080100300052 3.4000E+00 1.3100E-02 1.0000E-03 3080100300053 3.5000E+00 1.5600E-02 1.2000E-03 3080100300054 3.6000E+00 2.1600E-02 1.6000E-03 3080100300055 3.7000E+00 1.5000E-02 1.2000E-03 3080100300056 3.8000E+00 1.9100E-02 1.5000E-03 3080100300057 3.9000E+00 1.5900E-02 1.2000E-03 3080100300058 4.0000E+00 1.3600E-02 1.1000E-03 3080100300059 4.1000E+00 1.2900E-02 1.0000E-03 3080100300060 4.2000E+00 1.1300E-02 9.0000E-04 3080100300061 4.3000E+00 9.3400E-03 6.7000E-04 3080100300062 4.4000E+00 1.8000E-02 1.4000E-03 3080100300063 4.5000E+00 1.3300E-02 1.0000E-03 3080100300064 4.6000E+00 1.3500E-02 1.1000E-03 3080100300065 4.7000E+00 1.0400E-02 8.0000E-04 3080100300066 4.8000E+00 1.0200E-02 8.0000E-04 3080100300067 4.9000E+00 1.2400E-02 1.0000E-03 3080100300068 5.0000E+00 1.3400E-02 1.1000E-03 3080100300069 5.1000E+00 1.2500E-02 1.0000E-03 3080100300070 5.2000E+00 1.6600E-02 1.3000E-03 3080100300071 5.3000E+00 1.1200E-02 9.0000E-04 3080100300072 5.4000E+00 1.3400E-02 1.0000E-03 3080100300073 5.5000E+00 1.2100E-02 1.0000E-03 3080100300074 5.6000E+00 1.4800E-02 1.1000E-03 3080100300075 5.7000E+00 1.1700E-02 9.0000E-04 3080100300076 5.8000E+00 1.2900E-02 1.0000E-03 3080100300077 5.9000E+00 1.4500E-02 1.1000E-03 3080100300078 6.0000E+00 9.1300E-03 6.6000E-04 3080100300079 6.1000E+00 1.2600E-02 1.0000E-03 3080100300080 6.2000E+00 1.0100E-02 7.0000E-04 3080100300081 6.3000E+00 1.1000E-02 8.0000E-04 3080100300082 6.4000E+00 1.3700E-02 1.1000E-03 3080100300083 6.5000E+00 1.1700E-02 9.0000E-04 3080100300084 6.6000E+00 1.2700E-02 1.0000E-03 3080100300085 6.7000E+00 9.9000E-03 7.2000E-04 3080100300086 6.8000E+00 9.6800E-03 7.1000E-04 3080100300087 6.9000E+00 7.8000E-03 5.7000E-04 3080100300088 7.0000E+00 1.0600E-02 8.0000E-04 3080100300089 7.1000E+00 8.3100E-03 6.1000E-04 3080100300090 7.2000E+00 1.0200E-02 8.0000E-04 3080100300091 7.3000E+00 8.4500E-03 6.2000E-04 3080100300092 7.4000E+00 1.0200E-02 8.0000E-04 3080100300093 7.5000E+00 9.0100E-03 6.6000E-04 3080100300094 7.6000E+00 8.6700E-03 6.4000E-04 3080100300095 7.7000E+00 6.8900E-03 5.1000E-04 3080100300096 7.8000E+00 5.4900E-03 4.1000E-04 3080100300097 7.9000E+00 5.5900E-03 4.2000E-04 3080100300098 8.0000E+00 5.1400E-03 3.8000E-04 3080100300099 8.1000E+00 5.5100E-03 4.1000E-04 3080100300100 8.2000E+00 5.7200E-03 4.3000E-04 3080100300101 8.3000E+00 6.8200E-03 5.1000E-04 3080100300102 8.4000E+00 6.5800E-03 5.0000E-04 3080100300103 8.5000E+00 3.3900E-03 2.6000E-04 3080100300104 8.6000E+00 6.2400E-03 4.7000E-04 3080100300105 8.7000E+00 3.7300E-03 2.9000E-04 3080100300106 8.8000E+00 4.8600E-03 3.7000E-04 3080100300107 8.9000E+00 4.6400E-03 3.6000E-04 3080100300108 9.0000E+00 2.6300E-03 2.1000E-04 3080100300109 9.1000E+00 3.6100E-03 2.8000E-04 3080100300110 9.2000E+00 1.8100E-03 1.5000E-04 3080100300111 9.3000E+00 3.0100E-03 2.4000E-04 3080100300112 9.4000E+00 2.3800E-03 2.0000E-04 3080100300113 9.5000E+00 3.1400E-03 2.6000E-04 3080100300114 9.6000E+00 3.1500E-03 2.5000E-04 3080100300115 9.7000E+00 2.8600E-03 2.4000E-04 3080100300116 9.8000E+00 2.1100E-03 1.9000E-04 3080100300117 9.9000E+00 2.3400E-03 2.0000E-04 3080100300118 1.0000E+01 2.0700E-03 1.9000E-04 3080100300119 1.0100E+01 1.1600E-03 1.1000E-04 3080100300120 1.0200E+01 1.2800E-03 1.3000E-04 3080100300121 1.0300E+01 3.4900E-04 4.1000E-05 3080100300122 1.0400E+01 5.6700E-04 6.5000E-05 3080100300123 1.0500E+01 4.7300E-04 5.7000E-05 3080100300124 1.0600E+01 5.5000E-04 6.7000E-05 3080100300125 1.0700E+01 3.2800E-04 4.5000E-05 3080100300126 1.0800E+01 2.4300E-04 3.5000E-05 3080100300127 1.0900E+01 2.6800E-04 4.1000E-05 3080100300128 1.1000E+01 2.0800E-04 2.8000E-05 3080100300129 1.1500E+01 7.0900E-05 8.7000E-06 3080100300130 1.2000E+01 4.2200E-05 5.9000E-06 3080100300131 1.2500E+01 2.1200E-05 3.3000E-06 3080100300132 1.3000E+01 3.4300E-05 5.4000E-06 3080100300133 1.3500E+01 7.5000E-06 1.0000E-06 3080100300134 1.4000E+01 3.7100E-05 6.8000E-06 3080100300135 1.4500E+01 1.0600E-06 1.9000E-07 3080100300136 1.5000E+01 1.2600E-05 2.4000E-06 3080100300137 1.5500E+01 8.1000E-06 1.1000E-06 3080100300138 1.6000E+01 2.8200E-05 5.6000E-06 3080100300139 1.6500E+01 1.0100E-05 2.6000E-06 3080100300140 1.7000E+01 7.1000E-06 1.6000E-06 3080100300141 1.7500E+01 1.4600E-06 2.8000E-07 3080100300142 1.8000E+01 1.5000E-05 2.4000E-06 3080100300143 1.8500E+01 1.5900E-05 2.7000E-06 3080100300144 ENDDATA 126 0 3080100300145 ENDSUBENT 144 0 3080100399999 NOSUBENT 30801004 20090909 31413080100400001 SUBENT 30801005 20090909 31413080100500001 BIB 6 15 3080100500002 REFERENCE (J,IZV,46,(5),903,198205) Graph only 3080100500003 (J,BAS,46,(5),64,1982) English translation of IZV 3080100500004 (S,ZFK-459,153,1981) Graph only 3080100500005 Proceedings of Gaussig(1980) Conf. 3080100500006 (C,80KIEV,1,210,198009) Graph only 3080100500007 REACTION (26-FE-0(N,X)0-NN-1,PAR,MLT,G) 3080100500008 Average gamma-ray multiplicities of cascades following 3080100500009 emission of a neutron with specific energy 3080100500010 EN-SEC (E-MIN,N) 3080100500011 (E-MAX,N) 3080100500012 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 6. 3080100500013 ERR-ANALYS (DATA-ERR) Uncertainty of the boundaries of the neutron3080100500014 energy bins starts from 8% at 1 MeV and increases 3080100500015 to 29% at 12 MeV. 3080100500016 HISTORY (20090909A) OS. Added PAR to REACTION code 3080100500017 ENDBIB 15 0 3080100500018 NOCOMMON 0 0 3080100500019 DATA 4 9 3080100500020 E-MIN E-MAX DATA DATA-ERR 3080100500021 MEV MEV PRT/INC PRT/INC 3080100500022 1.0000E+00 2.0000E+00 2.2000E+00 5.0000E-01 3080100500023 2.0000E+00 3.0000E+00 2.9000E+00 3.0000E-01 3080100500024 3.0000E+00 4.0000E+00 3.1000E+00 5.0000E-01 3080100500025 4.0000E+00 5.0000E+00 3.3000E+00 6.0000E-01 3080100500026 5.0000E+00 6.0000E+00 3.2000E+00 7.0000E-01 3080100500027 6.0000E+00 7.0000E+00 3.6000E+00 7.0000E-01 3080100500028 7.0000E+00 8.0000E+00 3.3000E+00 6.0000E-01 3080100500029 8.0000E+00 1.0000E+01 2.5000E+00 5.0000E-01 3080100500030 1.0000E+01 1.2000E+01 2.2000E+00 5.0000E-01 3080100500031 ENDDATA 11 0 3080100500032 ENDSUBENT 31 0 3080100599999 SUBENT 30801006 20090909 31413080100600001 BIB 5 19 3080100600002 REACTION (28-NI-60(N,P)27-CO-60,PAR,DA,G) 3080100600003 Production cross section for discrete gamma-rays 3080100600004 measured at 90-deg. 3080100600005 REFERENCE (C,82SMOLEN,10,239,198206) Prelimin.data, graph only 3080100600006 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 7. 3080100600007 ERR-ANALYS (DATA-ERR) Over all 7. - 12. % 3080100600008 Following uncertainties are included: 3080100600009 Source of error Value(in %) 3080100600010 (ERR-1) No.of atoms in the sample 0.15 3080100600011 (ERR-2) Neutron flux 4. 3080100600012 (ERR-3,0.5,10.) Area of full energy peak (FEP) 0.5 - 103080100600013 (ERR-4) Efficiency in FEP 5. 3080100600014 (ERR-5) Corrections 3. 3080100600015 total 7. - 12. 3080100600016 HISTORY (20090909A) SD: Cosmetic changes, codes for partial 3080100600017 uncertainties and data to COMMON section are added. 3080100600018 Reaction code was changed. 3080100600019 Subent 006 were splited in several Subents 3080100600020 according to modified REACTION code. 3080100600021 ENDBIB 19 0 3080100600022 COMMON 5 3 3080100600023 ANG ERR-1 ERR-2 ERR-4 ERR-5 3080100600024 ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3080100600025 9.0000E+01 0.15 4. 5. 3. 3080100600026 ENDCOMMON 3 0 3080100600027 DATA 3 2 3080100600028 E DATA DATA-ERR 3080100600029 KEV MB/SR MB/SR 3080100600030 2.3000E+02 6.1000E-01 6.0000E-02 3080100600031 2.7700E+02 8.0000E-01 8.0000E-02 3080100600032 ENDDATA 4 0 3080100600033 ENDSUBENT 32 0 3080100699999 NOSUBENT 30801007 20090909 31413080100700001 SUBENT 30801008 20090909 31413080100800001 BIB 6 9 3080100800002 REFERENCE (C,82SMOLEN,10,239,198206) Graph only 3080100800003 REACTION (28-NI-58(N,X)0-NN-1,PAR,MLT,G) 3080100800004 Average gamma-ray multiplicities of cascades after 3080100800005 emission of a neutron with specific energy 3080100800006 EN-SEC (E-MIN,N) 3080100800007 (E-MAX,N) 3080100800008 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 9. 3080100800009 ERR-ANALYS (DATA-ERR) No further information 3080100800010 HISTORY (20090909A) OS. Added PAR to REACTION code 3080100800011 ENDBIB 9 0 3080100800012 NOCOMMON 0 0 3080100800013 DATA 4 8 3080100800014 E-MIN E-MAX DATA DATA-ERR 3080100800015 MEV MEV PRT/INC PRT/INC 3080100800016 2.0000E+00 3.0000E+00 9.0000E-01 5.0000E-01 3080100800017 3.0000E+00 4.0000E+00 7.0000E-01 5.0000E-01 3080100800018 4.0000E+00 5.0000E+00 2.0000E+00 3.0000E-01 3080100800019 5.0000E+00 6.0000E+00 1.9000E+00 3.0000E-01 3080100800020 6.0000E+00 7.0000E+00 3.9000E+00 6.0000E-01 3080100800021 7.0000E+00 8.0000E+00 4.5000E+00 8.0000E-01 3080100800022 8.0000E+00 1.0000E+01 3.0000E+00 5.0000E-01 3080100800023 1.0000E+01 1.2000E+01 2.5000E+00 4.0000E-01 3080100800024 ENDDATA 10 0 3080100800025 ENDSUBENT 24 0 3080100899999 SUBENT 30801009 20090909 31413080100900001 BIB 5 17 3080100900002 REACTION (26-FE-56(N,INL)26-FE-56,PAR,DA,G) 3080100900003 Production cross section for discrete gamma-ray 3080100900004 measured at 90 deg. 3080100900005 COMMENT Angle integrated production cross section for 847 keV 3080100900006 transition inferred from 90-deg.value and ang.distrib. 3080100900007 of ref.(Degtyarev+,Ukr.Fiz.Zh.22(1977)1463) is 3080100900008 560 +- 70 mb. 3080100900009 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 1. 3080100900010 ERR-ANALYS (DATA-ERR) Over all 7. - 12. % 3080100900011 Following uncertainties are included: 3080100900012 Source of error Value(in %) 3080100900013 (ERR-1) No.of atoms in the sample 0.15 3080100900014 (ERR-2) Neutron flux 4. 3080100900015 (ERR-3,0.5,10.) Area of full energy peak (FEP) 0.5 - 103080100900016 (ERR-4) Efficiency in FEP 5. 3080100900017 (ERR-5) Corrections 3. 3080100900018 HISTORY (20090909C) 3080100900019 ENDBIB 17 0 3080100900020 COMMON 5 3 3080100900021 ANG ERR-1 ERR-2 ERR-4 ERR-5 3080100900022 ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3080100900023 9.0000E+01 0.15 4. 5. 3. 3080100900024 ENDCOMMON 3 0 3080100900025 DATA 3 7 3080100900026 E DATA DATA-ERR 3080100900027 KEV MB/SR MB/SR 3080100900028 8.4700E+02 3.9200E+01 4.8000E+00 3080100900029 1.0380E+03 3.8400E+00 5.3000E-01 3080100900030 1.2380E+03 1.9600E+01 2.7000E+00 3080100900031 1.3030E+03 4.3200E+00 6.6000E-01 3080100900032 1.6710E+03 2.3900E+00 3.7000E-01 3080100900033 1.8110E+03 3.3200E+00 5.0000E-01 3080100900034 2.1130E+03 1.0200E+00 2.3000E-01 3080100900035 ENDDATA 9 0 3080100900036 ENDSUBENT 35 0 3080100999999 SUBENT 30801010 20090909 31413080101000001 BIB 5 15 3080101000002 REACTION (28-NI-58(N,P)27-CO-58,PAR,DA,G) 3080101000003 Production cross section for discrete gamma-rays 3080101000004 measured at 90-deg. 3080101000005 REFERENCE (C,82SMOLEN,10,239,198206) Prelimin.data, graph only 3080101000006 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 7. 3080101000007 ERR-ANALYS (DATA-ERR) Over all 7. - 12. % 3080101000008 Following uncertainties are included: 3080101000009 Source of error Value(in %) 3080101000010 (ERR-1) No.of atoms in the sample 0.15 3080101000011 (ERR-2) Neutron flux 4. 3080101000012 (ERR-3,0.5,10.) Area of full energy peak (FEP) 0.5 - 103080101000013 (ERR-4) Efficiency in FEP 5. 3080101000014 (ERR-5) Corrections 3. 3080101000015 total 7. - 12. 3080101000016 HISTORY (20090909C) 3080101000017 ENDBIB 15 0 3080101000018 COMMON 5 3 3080101000019 ANG ERR-1 ERR-2 ERR-4 ERR-5 3080101000020 ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3080101000021 9.0000E+01 0.15 4. 5. 3. 3080101000022 ENDCOMMON 3 0 3080101000023 DATA 3 7 3080101000024 E DATA DATA-ERR 3080101000025 KEV MB/SR MB/SR 3080101000026 3.2100E+02 1.2700E+00 1.0000E-01 3080101000027 3.6600E+02 1.2800E+00 9.0000E-02 3080101000028 4.3300E+02 1.4300E+00 1.2000E-01 3080101000029 7.2600E+02 6.1000E-01 6.0000E-02 3080101000030 7.7400E+02 4.1000E-01 5.0000E-02 3080101000031 8.3300E+02 5.9000E-01 7.0000E-02 3080101000032 1.0510E+03 1.6700E+00 1.6000E-01 3080101000033 ENDDATA 9 0 3080101000034 ENDSUBENT 33 0 3080101099999 SUBENT 30801011 20090909 31413080101100001 BIB 5 15 3080101100002 REACTION (28-NI-60(N,2N)28-NI-59,PAR,DA,G) 3080101100003 Production cross section for discrete gamma-rays 3080101100004 measured at 90-deg. 3080101100005 REFERENCE (C,82SMOLEN,10,239,198206) Prelimin.data, graph only 3080101100006 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 7. 3080101100007 ERR-ANALYS (DATA-ERR) Over all 7. - 12. % 3080101100008 Following uncertainties are included: 3080101100009 Source of error Value(in %) 3080101100010 (ERR-1) No.of atoms in the sample 0.15 3080101100011 (ERR-2) Neutron flux 4. 3080101100012 (ERR-3,0.5,10.) Area of full energy peak (FEP) 0.5 - 103080101100013 (ERR-4) Efficiency in FEP 5. 3080101100014 (ERR-5) Corrections 3. 3080101100015 total 7. - 12. 3080101100016 HISTORY (20090909C) 3080101100017 ENDBIB 15 0 3080101100018 COMMON 5 3 3080101100019 ANG ERR-1 ERR-2 ERR-4 ERR-5 3080101100020 ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3080101100021 9.0000E+01 0.15 4. 5. 3. 3080101100022 ENDCOMMON 3 0 3080101100023 DATA 3 3 3080101100024 E DATA DATA-ERR 3080101100025 KEV MB/SR MB/SR 3080101100026 3.3900E+02 8.4400E+00 7.2000E-01 3080101100027 8.7800E+02 1.8300E+00 1.6000E-01 3080101100028 1.1890E+03 2.1500E+00 3.2000E-01 3080101100029 ENDDATA 5 0 3080101100030 ENDSUBENT 29 0 3080101199999 SUBENT 30801012 20090909 31413080101200001 BIB 5 15 3080101200002 REACTION (28-NI-58(N,A)26-FE-55,PAR,DA,G) 3080101200003 Production cross section for discrete gamma-rays 3080101200004 measured at 90-deg. 3080101200005 REFERENCE (C,82SMOLEN,10,239,198206) Prelimin.data, graph only 3080101200006 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 7. 3080101200007 ERR-ANALYS (DATA-ERR) Over all 7. - 12. % 3080101200008 Following uncertainties are included: 3080101200009 Source of error Value(in %) 3080101200010 (ERR-1) No.of atoms in the sample 0.15 3080101200011 (ERR-2) Neutron flux 4. 3080101200012 (ERR-3,0.5,10.) Area of full energy peak (FEP) 0.5 - 103080101200013 (ERR-4) Efficiency in FEP 5. 3080101200014 (ERR-5) Corrections 3. 3080101200015 total 7. - 12. 3080101200016 HISTORY (20090909C) 3080101200017 ENDBIB 15 0 3080101200018 COMMON 5 3 3080101200019 ANG ERR-1 ERR-2 ERR-4 ERR-5 3080101200020 ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3080101200021 9.0000E+01 0.15 4. 5. 3. 3080101200022 ENDCOMMON 3 0 3080101200023 DATA 3 7 3080101200024 E DATA DATA-ERR 3080101200025 KEV MB/SR MB/SR 3080101200026 4.1200E+02 2.5000E-01 3.0000E-02 3080101200027 4.7800E+02 9.0000E-01 8.0000E-02 3080101200028 8.0300E+02 7.0000E-01 7.0000E-02 3080101200029 9.3100E+02 1.9100E+00 1.7000E-01 3080101200030 9.6100E+02 8.1000E-01 8.0000E-02 3080101200031 1.3170E+03 9.5000E-01 9.0000E-02 3080101200032 1.4090E+03 5.6000E-01 8.0000E-02 3080101200033 ENDDATA 9 0 3080101200034 ENDSUBENT 33 0 3080101299999 SUBENT 30801013 20090909 31413080101300001 BIB 5 15 3080101300002 REACTION (28-NI-58(N,X)27-CO-57,PAR,DA,G) 3080101300003 Production cross section for discrete gamma-rays 3080101300004 measured at 90-deg. 3080101300005 REFERENCE (C,82SMOLEN,10,239,198206) Prelimin.data, graph only 3080101300006 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 7. 3080101300007 ERR-ANALYS (DATA-ERR) Over all 7. - 12. % 3080101300008 Following uncertainties are included: 3080101300009 Source of error Value(in %) 3080101300010 (ERR-1) No.of atoms in the sample 0.15 3080101300011 (ERR-2) Neutron flux 4. 3080101300012 (ERR-3,0.5,10.) Area of full energy peak (FEP) 0.5 - 103080101300013 (ERR-4) Efficiency in FEP 5. 3080101300014 (ERR-5) Corrections 3. 3080101300015 total 7. - 12. 3080101300016 HISTORY (20090909C) 3080101300017 ENDBIB 15 0 3080101300018 COMMON 5 3 3080101300019 ANG ERR-1 ERR-2 ERR-4 ERR-5 3080101300020 ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3080101300021 9.0000E+01 0.15 4. 5. 3. 3080101300022 ENDCOMMON 3 0 3080101300023 DATA 3 7 3080101300024 E DATA DATA-ERR 3080101300025 KEV MB/SR MB/SR 3080101300026 4.6500E+02 1.4300E+00 1.1000E-01 3080101300027 6.7300E+02 5.3000E-01 6.0000E-02 3080101300028 1.2230E+03 7.6400E+00 5.1000E-01 3080101300029 1.3780E+03 2.3100E+00 1.7000E-01 3080101300030 1.6890E+03 7.9000E-01 8.0000E-02 3080101300031 1.7570E+03 7.2000E-01 8.0000E-02 3080101300032 1.9190E+03 6.4000E-01 8.0000E-02 3080101300033 ENDDATA 9 0 3080101300034 ENDSUBENT 33 0 3080101399999 SUBENT 30801014 20090909 31413080101400001 BIB 5 15 3080101400002 REACTION (28-NI-58(N,INL)28-NI-58,PAR,DA,G) 3080101400003 Production cross section for discrete gamma-rays 3080101400004 measured at 90-deg. 3080101400005 REFERENCE (C,82SMOLEN,10,239,198206) Prelimin.data, graph only 3080101400006 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 7. 3080101400007 ERR-ANALYS (DATA-ERR) Over all 7. - 12. % 3080101400008 Following uncertainties are included: 3080101400009 Source of error Value(in %) 3080101400010 (ERR-1) No.of atoms in the sample 0.15 3080101400011 (ERR-2) Neutron flux 4. 3080101400012 (ERR-3,0.5,10.) Area of full energy peak (FEP) 0.5 - 103080101400013 (ERR-4) Efficiency in FEP 5. 3080101400014 (ERR-5) Corrections 3. 3080101400015 total 7. - 12. 3080101400016 HISTORY (20090909C) 3080101400017 ENDBIB 15 0 3080101400018 COMMON 5 3 3080101400019 ANG ERR-1 ERR-2 ERR-4 ERR-5 3080101400020 ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3080101400021 9.0000E+01 0.15 4. 5. 3. 3080101400022 ENDCOMMON 3 0 3080101400023 DATA 3 7 3080101400024 E DATA DATA-ERR 3080101400025 KEV MB/SR MB/SR 3080101400026 7.4500E+02 4.9000E-01 7.0000E-02 3080101400027 7.6200E+02 6.3000E-01 6.0000E-02 3080101400028 9.6100E+02 8.1000E-01 8.0000E-02 3080101400029 1.0050E+03 6.2100E+00 4.5000E-01 3080101400030 1.1600E+03 1.6600E+00 1.6000E-01 3080101400031 1.3210E+03 8.0000E-01 8.0000E-02 3080101400032 1.4540E+03 1.5900E+01 1.2000E+00 3080101400033 ENDDATA 9 0 3080101400034 ENDSUBENT 33 0 3080101499999 SUBENT 30801015 20090909 31413080101500001 BIB 5 15 3080101500002 REACTION (28-NI-60(N,INL)28-NI-60,PAR,DA,G) 3080101500003 Production cross section for discrete gamma-rays 3080101500004 measured at 90-deg. 3080101500005 REFERENCE (C,82SMOLEN,10,239,198206) Prelimin.data, graph only 3080101500006 STATUS (TABLE) Data taken from INDC(CSR)-5 (1983),Table 7. 3080101500007 ERR-ANALYS (DATA-ERR) Over all 7. - 12. % 3080101500008 Following uncertainties are included: 3080101500009 Source of error Value(in %) 3080101500010 (ERR-1) No.of atoms in the sample 0.15 3080101500011 (ERR-2) Neutron flux 4. 3080101500012 (ERR-3,0.5,10.) Area of full energy peak (FEP) 0.5 - 103080101500013 (ERR-4) Efficiency in FEP 5. 3080101500014 (ERR-5) Corrections 3. 3080101500015 total 7. - 12. 3080101500016 HISTORY (20090909C) 3080101500017 ENDBIB 15 0 3080101500018 COMMON 5 3 3080101500019 ANG ERR-1 ERR-2 ERR-4 ERR-5 3080101500020 ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3080101500021 9.0000E+01 0.15 4. 5. 3. 3080101500022 ENDCOMMON 3 0 3080101500023 DATA 3 3 3080101500024 E DATA DATA-ERR 3080101500025 KEV MB/SR MB/SR 3080101500026 8.2600E+02 6.0500E+00 4.7000E-01 3080101500027 1.1730E+03 1.9300E+01 1.2000E+00 3080101500028 1.3320E+03 4.0600E+01 3.6000E+00 3080101500029 ENDDATA 5 0 3080101500030 ENDSUBENT 29 0 3080101599999 ENDENTRY 15 0 3080199999999