ENTRY 30806 20090910 31413080600000001 SUBENT 30806001 20090910 31413080600100001 BIB 11 19 3080600100002 INSTITUTE (3PAKNIL) 3080600100003 REFERENCE (P,INDC(PAK)-005,14,198407) Report on the IAEA research3080600100004 contract 3310/R1/RB 3080600100005 AUTHOR (K.Gul,M.Ahmad,M.Anwar,S.M.Saleem,Naeem A.Khan) 3080600100006 TITLE Production cross-sections of gamma-rays emitted from 3080600100007 Fe on bombardment with 14.7 MeV neutrons 3080600100008 FACILITY (CCW) 3080600100009 INC-SOURCE (D-T) 3080600100010 SAMPLE Natural metallic sample of 7.6 cm diameter and 7.6 cm 3080600100011 high 3080600100012 DETECTOR (GELI) 100.cm3 with absolute efficiency determined 3080600100013 on the research reactor using the reactions 3080600100014 17-Cl-35(n,g)17-Cl-36 and 7-N-14(n,g)7-N-15 and 3080600100015 standard radioactive sources. 3080600100016 STATUS (TABLE) Data were taken from Table 1 of the reference 3080600100017 HISTORY (19840712C) by VP 3080600100018 (20090725A) SD:Updated to new date formats,lower case. 3080600100019 CORRECTION Yields of gamma-rays were corrected for efficiency and 3080600100020 attenuation effects 3080600100021 ENDBIB 19 0 3080600100022 COMMON 1 3 3080600100023 EN 3080600100024 MEV 3080600100025 1.4700E+01 3080600100026 ENDCOMMON 3 0 3080600100027 ENDSUBENT 26 0 3080600199999 SUBENT 30806002 20090910 31413080600200001 BIB 1 4 3080600200002 REACTION (26-FE-0(N,X)0-G-0,,SPC,,REL) The intensity of the 3080600200003 847.keV gamma-line was taken for 100. 3080600200004 No information about the angle between the neutron- 3080600200005 beam and observed gammas 3080600200006 ENDBIB 4 0 3080600200007 NOCOMMON 0 0 3080600200008 DATA 3 43 3080600200009 E DATA DATA-ERR 3080600200010 KEV ARB-UNITS ARB-UNITS 3080600200011 4.3800E+02 1.6000E+00 4.0000E-01 3080600200012 4.7500E+02 1.9000E+00 5.0000E-01 3080600200013 5.6700E+02 1.0000E+00 4.0000E-01 3080600200014 6.9800E+02 9.4000E+00 6.0000E-01 3080600200015 8.4700E+02 1.0000E+02 8.0000E-01 3080600200016 9.3100E+02 1.0700E+01 6.0000E-01 3080600200017 1.0100E+03 1.3000E+00 4.0000E-01 3080600200018 1.0380E+03 1.0400E+01 9.0000E-01 3080600200019 1.1750E+03 1.1000E+00 4.0000E-01 3080600200020 1.2380E+03 5.0100E+01 2.5000E+00 3080600200021 1.3100E+03 1.6500E+01 5.0000E-01 3080600200022 1.3600E+03 1.2000E+00 3.0000E-01 3080600200023 1.4080E+03 3.1000E+00 3.0000E-01 3080600200024 1.5810E+03 5.0000E-01 3.0000E-01 3080600200025 1.6700E+03 3.8000E+00 3.0000E-01 3080600200026 1.7280E+03 4.0000E-01 3.0000E-01 3080600200027 1.7750E+03 1.3000E+00 2.0000E-01 3080600200028 1.8110E+03 9.3000E+00 7.0000E-01 3080600200029 1.8610E+03 4.0000E-01 3.0000E-01 3080600200030 2.0350E+03 2.4000E+00 1.2000E+00 3080600200031 2.1130E+03 1.7000E+00 3.0000E-01 3080600200032 2.2170E+03 2.5000E+00 3.0000E-01 3080600200033 2.2730E+03 1.2000E+00 3.0000E-01 3080600200034 2.3740E+03 5.0000E-01 3.0000E-01 3080600200035 2.4250E+03 8.0000E-01 3.0000E-01 3080600200036 2.4690E+03 6.0000E-01 2.0000E-01 3080600200037 2.5260E+03 2.4000E+00 3.0000E-01 3080600200038 2.5990E+03 4.6000E+00 6.0000E-01 3080600200039 2.7590E+03 1.5000E+00 4.0000E-01 3080600200040 2.9560E+03 9.0000E-01 3.0000E-01 3080600200041 2.9850E+03 8.0000E-01 2.0000E-01 3080600200042 3.0630E+03 8.0000E-01 2.0000E-01 3080600200043 3.2030E+03 1.0000E+00 4.0000E-01 3080600200044 3.2540E+03 1.5000E+00 4.0000E-01 3080600200045 3.4500E+03 1.2000E+00 3.0000E-01 3080600200046 3.5540E+03 4.0000E-01 3.0000E-01 3080600200047 3.6120E+03 1.6000E+00 3.0000E-01 3080600200048 3.6630E+03 1.0000E+00 4.0000E-01 3080600200049 3.8350E+03 1.0000E+00 5.0000E-01 3080600200050 5.0950E+03 9.0000E-01 4.0000E-01 3080600200051 6.7470E+03 9.0000E-01 4.0000E-01 3080600200052 7.0910E+03 7.0000E-01 4.0000E-01 3080600200053 8.8000E+03 6.0000E-01 3.0000E-01 3080600200054 ENDDATA 45 0 3080600200055 ENDSUBENT 54 0 3080600299999 ENDENTRY 2 0 3080699999999