ENTRY 40187 20150109 41724018700000001 SUBENT 40187001 20150109 41724018700100001 BIB 14 30 4018700100002 INSTITUTE (4RUSFEI) 4018700100003 REFERENCE (J,SNP,15,1,1972) Eng.transl.of YF,15,(1),3,1972 4018700100004 (J,YF,15,(1),3,1972) Schemes of levels and data 4018700100005 are given 4018700100006 AUTHOR (A.F.Gamalii,B.V.Zemtsev,V.B.Ivanov,B.V.Nesterov, 4018700100007 L.P.Kham'yanov) 4018700100008 TITLE Gamma-radiation in intermediate neutron radiative 4018700100009 capture. 4018700100010 FACILITY (REAC,4RUSFEI) Reactor 4018700100011 METHOD Direct detection of gammas 4018700100012 DETECTOR (GELI) Germanium-lithium detector with sensible 4018700100013 volume 16 cm**3 . 4018700100014 Resolution of detector was 5 keV at 1 MeV and 15 keV 4018700100015 at 10 MeV 4018700100016 PART-DET (G) Gammas 4018700100017 ANALYSIS Area analysis 4018700100018 MONITOR Standard sources Ta-182 and Co-56 and gamma-rays from 4018700100019 the reaction Cr-51(n,gamma) 4018700100020 ERR-ANALYS No errors are given in the article. 4018700100021 ADD-RES Levels schemes for Mo-96 (fig.2), Ti-49 (fig.3) 4018700100022 STATUS (TABLE) Data from authors. 4018700100023 HISTORY (19731207C) Compiled at the centre 4018700100024 (19750210A) Corrections in Subentries 002 and 003 made 4018700100025 (20010307A) Updated to new date formats. Institute 4018700100026 updated. 4018700100027 (20150109A) SD: Ref.on Engl.transl.of YF added.Author's4018700100028 names corrected (L.P.KHAM JANOV -> L.P.Kham'yanov; 4018700100029 GAMALIJ -> Gamalii). REACTION correction in Sub.2-8. 4018700100030 (20151105A) M.M. Article was checked, BIB information 4018700100031 was updated in TITLE,DETECTOR,ANALYSIS,STATUS, ADD-RES 4018700100032 ENDBIB 30 0 4018700100033 NOCOMMON 0 0 4018700100034 ENDSUBENT 33 0 4018700199999 SUBENT 40187002 20150109 41724018700200001 BIB 5 15 4018700200002 REACTION ((42-MO-95(N,G)42-MO-96,,SPC)// 4018700200003 (42-MO-95(N,G)42-MO-96,,SPC)) 4018700200004 Gamma-rays intensities are given 4018700200005 relative to value at 778 keV gamma-line 4018700200006 which intensity was taken as 100. - 4018700200007 intensities were divided by 100 to obtain NO-DIM units.4018700200008 INC-SOURCE Neutrons were selected from the solid spectrum of the 4018700200009 reactor by means of the filter made of 600 mm quartz 4018700200010 and 100-300 mm bismuth 4018700200011 SAMPLE (42-MO-95,ENR=0.836) 33.6 gram oxide of MoO3, Mo-95 4018700200012 83.6% enriched, diam.30. mm. 4018700200013 STATUS (TABLE) Data are on Fig.2 of YF,15,(1),3,1972 4018700200014 HISTORY (20150109A) SD: REACTION code changed on ratio. DATA 4018700200015 units changed (ARB-UNITS -> NO-DIM). 4018700200016 (20151105A) M.M. Intensities were divided by 100. 4018700200017 ENDBIB 15 0 4018700200018 COMMON 2 3 4018700200019 EN-DUMMY E-DN 4018700200020 EV KEV 4018700200021 2.53E-02 778. 4018700200022 ENDCOMMON 3 0 4018700200023 DATA 2 27 4018700200024 E-NM DATA 4018700200025 KEV NO-DIM 4018700200026 2.4100E+02 1.2000E-02 4018700200027 3.5100E+02 1.2500E-02 4018700200028 3.7200E+02 1.9000E-02 4018700200029 4.8000E+02 3.0000E-02 4018700200030 6.1100E+02 6.0000E-02 4018700200031 7.1900E+02 1.5000E-01 4018700200032 7.3700E+02 5.0000E-02 4018700200033 7.4600E+02 1.0000E-02 4018700200034 7.7800E+02 1.00 4018700200035 8.4900E+02 4.1000E-01 4018700200036 9.6800E+02 3.3000E-02 4018700200037 1.0890E+03 1.0000E-01 4018700200038 1.2000E+03 8.0000E-02 4018700200039 1.4980E+03 4.7000E-02 4018700200040 1.6250E+03 1.8000E-02 4018700200041 1.7030E+03 2.1000E-02 4018700200042 1.7620E+03 5.0000E-03 4018700200043 1.9220E+03 5.0000E-03 4018700200044 2.6640E+03 5.0000E-03 4018700200045 5.6020E+03 2.4200E-02 4018700200046 5.7100E+03 6.5000E-02 4018700200047 6.3630E+03 2.6000E-02 4018700200048 6.6740E+03 1.6000E-02 4018700200049 6.9200E+03 1.3400E-01 4018700200050 7.5260E+03 3.0000E-02 4018700200051 7.6560E+03 1.0000E-02 4018700200052 8.3750E+03 3.7500E-02 4018700200053 ENDDATA 29 0 4018700200054 ENDSUBENT 53 0 4018700299999 SUBENT 40187003 20150109 41724018700300001 BIB 5 15 4018700300002 REACTION ((42-MO-95(N,G)42-MO-96,,SPC)// 4018700300003 (42-MO-95(N,G)42-MO-96,,SPC)) 4018700300004 Gamma-rays intensities are given 4018700300005 relative to value at 778 keV gamma-line 4018700300006 which intensity was taken as 100. - 4018700300007 intensities were divided by 100 to obtain NO-DIM units.4018700300008 INC-SOURCE Neutrons were selected from the solid spectrum of the 4018700300009 reactor by means of scandium filter 70 cm thickness 4018700300010 SAMPLE (42-MO-95,ENR=0.836) 33.6 gram oxide of MoO3, Mo-95 4018700300011 83.6% enriched, diam.30. mm. 4018700300012 STATUS (TABLE) Data are on Fig.2 of YF,15,(1),3,1972 4018700300013 HISTORY (20150109A) SD: REACTION code changed on ratio. DATA 4018700300014 units changed (ARB-UNITS -> NO-DIM). 4018700300015 (20151105A) M.M. Intensities were divided by 100. 4018700300016 EN-RSL was added. 4018700300017 ENDBIB 15 0 4018700300018 COMMON 3 3 4018700300019 EN E-DN EN-RSL-HW 4018700300020 KEV KEV EV 4018700300021 2. 778. 900. 4018700300022 ENDCOMMON 3 0 4018700300023 DATA 2 20 4018700300024 E-NM DATA 4018700300025 KEV NO-DIM 4018700300026 3.5100E+02 1.0000E-02 4018700300027 3.7200E+02 3.7000E-02 4018700300028 7.1900E+02 1.2800E-01 4018700300029 7.3700E+02 1.0000E-02 4018700300030 7.7800E+02 1. 4018700300031 8.4800E+02 3.5000E-01 4018700300032 1.0900E+03 9.0000E-02 4018700300033 1.2000E+03 8.5000E-02 4018700300034 1.4970E+03 2.0000E-02 4018700300035 1.7010E+03 5.0000E-03 4018700300036 1.7600E+03 5.0000E-03 4018700300037 2.0080E+03 5.0000E-03 4018700300038 6.3630E+03 8.0000E-03 4018700300039 6.9230E+03 1.5000E-02 4018700300040 7.1780E+03 1.0000E-02 4018700300041 7.2850E+03 5.0000E-03 4018700300042 7.5280E+03 1.3000E-02 4018700300043 7.6550E+03 1.6000E-02 4018700300044 8.3760E+03 1.4000E-02 4018700300045 9.1540E+03 5.0000E-03 4018700300046 ENDDATA 22 0 4018700300047 ENDSUBENT 46 0 4018700399999 SUBENT 40187004 20150109 41724018700400001 BIB 5 16 4018700400002 REACTION ((42-MO-95(N,G)42-MO-96,,SPC)// 4018700400003 (42-MO-95(N,G)42-MO-96,,SPC)) 4018700400004 Gamma-rays intensities are given 4018700400005 relative to value at 778 keV gamma-line 4018700400006 which intensity was taken as 100. - 4018700400007 intensities were divided by 100 to obtain NO-DIM units.4018700400008 INC-SOURCE Neutrons were selected from the solid spectrum of the 4018700400009 reactor by means of the filter made of 18 cm Fe, 4018700400010 16 cm Al and 10 cm S 4018700400011 SAMPLE (42-MO-95,ENR=0.836) 33.6 gram oxide of MoO3, Mo-95 4018700400012 83.6% enriched, diam.30. mm. 4018700400013 STATUS (TABLE) Data are on Fig.2 of YF,15,(1),3,1972 4018700400014 HISTORY (20150109A) SD: REACTION code changed on ratio. DATA 4018700400015 units changed (ARB-UNITS -> NO-DIM). 4018700400016 (20151105A) M.M. Intensities were divided by 100. 4018700400017 EN-RSL was added. 4018700400018 ENDBIB 16 0 4018700400019 COMMON 3 3 4018700400020 EN E-DN EN-RSL-HW 4018700400021 KEV KEV KEV 4018700400022 25. 778. 2.5 4018700400023 ENDCOMMON 3 0 4018700400024 DATA 2 11 4018700400025 E-NM DATA 4018700400026 KEV NO-DIM 4018700400027 3.7200E+02 5.0000E-03 4018700400028 7.1900E+02 1.1300E-01 4018700400029 7.3700E+02 1.0000E-02 4018700400030 7.7800E+02 1.00 4018700400031 8.4800E+02 4.2200E-01 4018700400032 1.0890E+03 1.1700E-01 4018700400033 1.2000E+03 5.9000E-02 4018700400034 1.5000E+03 5.6000E-02 4018700400035 7.5490E+03 1.3300E-02 4018700400036 8.3980E+03 1.9000E-02 4018700400037 9.1740E+03 8.0000E-03 4018700400038 ENDDATA 13 0 4018700400039 ENDSUBENT 38 0 4018700499999 SUBENT 40187005 20150109 41724018700500001 BIB 5 18 4018700500002 REACTION ((42-MO-97(N,G)42-MO-98,,SPC)// 4018700500003 (42-MO-97(N,G)42-MO-98,,SPC)) 4018700500004 Gamma-ray intensities are given 4018700500005 relative to value at 787 keV gamma-line, 4018700500006 which intensity was taken as 100. in the article - 4018700500007 intensities were divided by 100 to obtain NO-DIM units.4018700500008 INC-SOURCE Neutrons were selected from the solid spectrum of the 4018700500009 reactor by means of the filter made of 600 mm quartz 4018700500010 and 100-300 mm bismuth 4018700500011 SAMPLE (42-MO-97,ENR=0.699) 33.6 gram oxide of MoO3, Mo-97 4018700500012 69.9% enriched, diam.30. mm. 4018700500013 STATUS (TABLE) Table of SNP,15,1,1972 4018700500014 HISTORY (20010307A) Lines with blank data fields deleted. 4018700500015 Flag deleted. 4018700500016 (20150109A) SD: REACTION code changed on ratio. DATA 4018700500017 units changed (ARB-UNITS -> NO-DIM). SAMPLE added. 4018700500018 (20151105A) M.M. Two points were moved in DATA-MAX, 4018700500019 STATUS was added. Intensities were divided by 100. 4018700500020 ENDBIB 18 0 4018700500021 COMMON 2 3 4018700500022 EN-DUMMY E-DN 4018700500023 EV KEV 4018700500024 2.53E-02 787. 4018700500025 ENDCOMMON 3 0 4018700500026 DATA 3 13 4018700500027 E-NM DATA DATA-MAX 4018700500028 KEV NO-DIM NO-DIM 4018700500029 7.23E+02 3.46 E-01 4018700500030 7.87E+02 1.00 4018700500031 9.70E+02 4.35 E-02 4018700500032 1.024E+03 1.87 E-01 4018700500033 1.230E+03 1.66 E-01 4018700500034 1.318E+03 1. E-02 4018700500035 1.419E+03 3.3 E-02 4018700500036 1.431E+03 9.7 E-02 4018700500037 1.544E+03 3.15 E-02 4018700500038 5.685E+03 1.5 E-02 4018700500039 5.875E+03 5. E-03 4018700500040 6.623E+03 1.22 E-01 4018700500041 7.910E+03 5. E-03 4018700500042 ENDDATA 15 0 4018700500043 ENDSUBENT 42 0 4018700599999 SUBENT 40187006 20150109 41724018700600001 BIB 5 16 4018700600002 REACTION ((42-MO-97(N,G)42-MO-98,,SPC)// 4018700600003 (42-MO-97(N,G)42-MO-98,,SPC)) 4018700600004 Gamma-rays intensities are given 4018700600005 relative to value at 786 keV gamma-line 4018700600006 which intensity was taken as 100. in the article - 4018700600007 intensities were divided by 100 to obtain NO-DIM units.4018700600008 INC-SOURCE Neutron were selected from the solid spectrum of the 4018700600009 reactor by means of scandium filter 70 cm thickness 4018700600010 SAMPLE (42-MO-97,ENR=0.699) 33.6 gram oxide of MoO3, Mo-97 4018700600011 69.9% enriched, diam.30. mm. 4018700600012 STATUS (TABLE) Table of SNP,15,1,1972 4018700600013 HISTORY (20150109A) SD: REACTION code changed on ratio. DATA 4018700600014 units changed (ARB-UNITS -> NO-DIM). SAMPLE added. 4018700600015 (20151105A) M.M. Two points were moved in DATA-MAX, 4018700600016 STATUS was added. Intensities were divided by 100. 4018700600017 EN-RSL was added. 4018700600018 ENDBIB 16 0 4018700600019 COMMON 3 3 4018700600020 EN E-DN EN-RSL-HW 4018700600021 KEV KEV EV 4018700600022 2. 786. 900. 4018700600023 ENDCOMMON 3 0 4018700600024 DATA 3 19 4018700600025 E-NM DATA DATA-MAX 4018700600026 KEV NO-DIM NO-DIM 4018700600027 6.44E+02 1. E-02 4018700600028 7.23E+02 3.7E-01 4018700600029 7.86E+02 1.00 4018700600030 9.70E+02 2.6E-02 4018700600031 1.023E+03 6.1E-02 4018700600032 1.235E+03 6.0E-02 4018700600033 1.434E+03 1. E-02 4018700600034 1.545E+03 4.8E-02 4018700600035 5.685E+03 8. E-03 4018700600036 6.017E+03 2.0E-02 4018700600037 6.418E+03 1.5E-02 4018700600038 6.536E+03 1.5E-02 4018700600039 6.623E+03 1.5E-02 4018700600040 6.885E+03 8. E-03 4018700600041 7.133E+03 1.0E-02 4018700600042 7.212E+03 8. E-03 4018700600043 7.277E+03 8. E-03 4018700600044 7.855E+03 1.1E-02 4018700600045 7.910E+03 1.1E-02 4018700600046 ENDDATA 21 0 4018700600047 ENDSUBENT 46 0 4018700699999 SUBENT 40187007 20150109 41724018700700001 BIB 5 17 4018700700002 REACTION ((42-MO-97(N,G)42-MO-98,,SPC)// 4018700700003 (42-MO-97(N,G)42-MO-98,,SPC)) 4018700700004 Gamma-rays intensities are given 4018700700005 relative to value at 788 keV gamma-line, 4018700700006 which intensity was taken as 100. in the article - 4018700700007 intensities were divided by 100 to obtain NO-DIM units.4018700700008 INC-SOURCE Neutrons were selected from the solid spectrum of the 4018700700009 reactor by means of the filter made of 18 cm Fe, 4018700700010 16 cm Al and 10 cm S 4018700700011 SAMPLE (42-MO-97,ENR=0.699) 33.6 gram oxide of MoO3, Mo-97 4018700700012 69.9% enriched, diam.30. mm. 4018700700013 STATUS (TABLE) Table of SNP,15,1,1972 4018700700014 HISTORY (20150109A) SD: REACTION code changed on ratio. DATA 4018700700015 units changed (ARB-UNITS -> NO-DIM). SAMPLE added. 4018700700016 (20151105A) M.M. One point was moved in DATA-MAX, 4018700700017 STATUS was added. Intensities were divided by 100. 4018700700018 EN-RSL was added. 4018700700019 ENDBIB 17 0 4018700700020 COMMON 3 3 4018700700021 EN E-DN EN-RSL-HW 4018700700022 KEV KEV KEV 4018700700023 25. 788. 2.5 4018700700024 ENDCOMMON 3 0 4018700700025 DATA 3 10 4018700700026 E-NM DATA DATA-MAX 4018700700027 KEV NO-DIM NO-DIM 4018700700028 4.81E+02 9.1 E-02 4018700700029 6.45E+02 4.2 E-02 4018700700030 6.61E+02 1.18E-01 4018700700031 7.23E+02 2.44E-01 4018700700032 7.88E+02 1.00 4018700700033 1.023E+03 8.7 E-02 4018700700034 1.230E+03 3.6 E-02 4018700700035 1.430E+03 4. E-02 4018700700036 1.543E+03 2.64E-02 4018700700037 7.882E+03 5. E-03 4018700700038 ENDDATA 12 0 4018700700039 ENDSUBENT 38 0 4018700799999 SUBENT 40187008 20150109 41724018700800001 BIB 5 15 4018700800002 REACTION ((28-NI-62(N,G)28-NI-63,,SPC)// 4018700800003 (28-NI-62(N,G)28-NI-63,,SPC)) 4018700800004 Gamma-rays intensities are given 4018700800005 relative to value at 6840 keV gamma-line 4018700800006 which intensity was taken as 100. - 4018700800007 intensities were divided by 100 to obtain NO-DIM units.4018700800008 INC-SOURCE Neutrons were selected from the solid spectrum of the 4018700800009 reactor by means of scandium filter 70 cm thickness 4018700800010 SAMPLE (28-NI-62,ENR=0.972) 30. gram nickel oxide, 4018700800011 97.2% enriched , diam.30. mm. 4018700800012 STATUS (TABLE) Text, page 7 of YF,15,(1),3,1972 4018700800013 HISTORY (20150109A) SD: REACTION code changed on ratio. DATA 4018700800014 units changed (ARB-UNITS -> NO-DIM). SAMPLE added. 4018700800015 (20151105A) M.M. Intensities were divided by 100. 4018700800016 EN-RSL was added. 4018700800017 ENDBIB 15 0 4018700800018 COMMON 3 3 4018700800019 EN E-DN EN-RSL-HW 4018700800020 KEV KEV EV 4018700800021 2. 6840. 900. 4018700800022 ENDCOMMON 3 0 4018700800023 DATA 2 5 4018700800024 E-NM DATA 4018700800025 KEV NO-DIM 4018700800026 1.5600E+02 7.0000E-02 4018700800027 3.6200E+02 6.6000E-02 4018700800028 8.4500E+02 7.0000E-02 4018700800029 1.1700E+03 2.6000E-01 4018700800030 6.8400E+03 1.00 4018700800031 ENDDATA 7 0 4018700800032 ENDSUBENT 31 0 4018700899999 SUBENT 40187009 20150109 41724018700900001 BIB 5 13 4018700900002 REACTION (22-TI-48(N,G)22-TI-49,,SPC,,REL) 4018700900003 Gamma-rays intensities are given 4018700900004 relative to summary intensity of gamma-transitions at 4018700900005 1382 keV, 1586 keV and 1762 keV ( sum=100.) 4018700900006 INC-SOURCE Neutrons were selected from the solid spectrum of the 4018700900007 reactor by means of the filter made of 600 mm quartz 4018700900008 and 100-300 mm bismuth 4018700900009 SAMPLE (22-TI-48,ENR=0.7399) 80. gram in metal form, 4018700900010 73.99% enriched , diam.30. mm. 4018700900011 STATUS (TABLE) Data are on Fig.3 of YF,15,(1),3,1972 4018700900012 HISTORY (20010307A) Lines with blank data fields deleted. 4018700900013 Flag deleted. 4018700900014 (20150109A) SD: SAMPLE added. 4018700900015 ENDBIB 13 0 4018700900016 COMMON 1 3 4018700900017 EN-DUMMY 4018700900018 EV 4018700900019 2.53 E-02 4018700900020 ENDCOMMON 3 0 4018700900021 DATA 2 10 4018700900022 E DATA 4018700900023 KEV ARB-UNITS 4018700900024 3.4200E+02 2.2400E+01 4018700900025 1.3820E+03 8.9000E+01 4018700900026 1.4980E+03 4.2000E+00 4018700900027 1.5860E+03 1.0200E+01 4018700900028 1.7620E+03 5.8000E+00 4018700900029 4.8810E+03 4.0000E+00 4018700900030 4.9670E+03 2.5000E+00 4018700900031 6.4170E+03 3.1500E+01 4018700900032 6.5570E+03 5.5000E+00 4018700900033 6.7610E+03 5.9000E+01 4018700900034 ENDDATA 12 0 4018700900035 ENDSUBENT 34 0 4018700999999 SUBENT 40187010 20150109 41724018701000001 BIB 5 13 4018701000002 REACTION (22-TI-48(N,G)22-TI-49,,SPC,,REL) 4018701000003 Gamma-rays intensities are given 4018701000004 relative to summary intensity of gamma-transitions at 4018701000005 1382 keV,1586 keV and 1762 keV ( sum=100.) 4018701000006 INC-SOURCE Neutrons were selected from the solid spectrum of the 4018701000007 reactor by means of scandium filter 70 cm thickness 4018701000008 SAMPLE (22-TI-48,ENR=0.7399) 80. gram in metal form, 4018701000009 73.99% enriched , diam.30. mm. 4018701000010 STATUS (TABLE) Data are on Fig.3 of YF,15,(1),3,1972 4018701000011 HISTORY (20010307A) Lines with blank data fields deleted. 4018701000012 Flag deleted. 4018701000013 (20150109A) SD: SAMPLE added. 4018701000014 (20151105A) M.M. EN-RSL was added. 4018701000015 ENDBIB 13 0 4018701000016 COMMON 2 3 4018701000017 EN EN-RSL-HW 4018701000018 KEV EV 4018701000019 2. 900. 4018701000020 ENDCOMMON 3 0 4018701000021 DATA 2 7 4018701000022 E DATA 4018701000023 KEV ARB-UNITS 4018701000024 1.3820E+03 8.4000E+01 4018701000025 1.5860E+03 8.6000E+00 4018701000026 1.7620E+03 7.4000E+00 4018701000027 4.8810E+03 7.1000E+00 4018701000028 6.4170E+03 4.1000E+01 4018701000029 6.5570E+03 4.2500E+00 4018701000030 6.7610E+03 6.8500E+01 4018701000031 ENDDATA 9 0 4018701000032 ENDSUBENT 31 0 4018701099999 SUBENT 40187011 20150109 41724018701100001 BIB 5 12 4018701100002 REACTION (22-TI-48(N,G)22-TI-49,,SPC,,REL) 4018701100003 Gamma-rays intensities are given 4018701100004 relative to summary intensity of gamma-transitions at 4018701100005 1382 keV,1586 keV and 1762 keV (sum=100.) 4018701100006 INC-SOURCE Neutrons were selected from the solid spectrum of the 4018701100007 reactor by means of the filter made of 18 cm Fe, 4018701100008 16 cm Al and 10 cm S 4018701100009 SAMPLE (22-TI-48,ENR=0.7399) 80. gram in metal form, 4018701100010 73.99% enriched, diam.30. mm. 4018701100011 STATUS (TABLE) Data are on Fig.3 of YF,15,(1),3,1972 4018701100012 HISTORY (20150109A) SD: SAMPLE added. 4018701100013 (20151105A) M.M. EN-RSL was added. 4018701100014 ENDBIB 12 0 4018701100015 COMMON 2 3 4018701100016 EN EN-RSL-HW 4018701100017 KEV KEV 4018701100018 25. 2.5 4018701100019 ENDCOMMON 3 0 4018701100020 DATA 2 7 4018701100021 E DATA 4018701100022 KEV ARB-UNITS 4018701100023 3.4200E+02 2.4000E+01 4018701100024 1.3820E+03 8.0000E+01 4018701100025 1.5860E+03 1.4200E+01 4018701100026 1.7620E+03 5.8000E+00 4018701100027 6.4320E+03 2.9000E+01 4018701100028 6.5740E+03 6.8000E+00 4018701100029 6.7760E+03 3.0000E+01 4018701100030 ENDDATA 9 0 4018701100031 ENDSUBENT 30 0 4018701199999 ENDENTRY 11 0 4018799999999