ENTRY 30901 20220203 32073090100000001 SUBENT 30901001 20220203 32073090100100001 BIB 14 29 3090100100002 TITLE Neutron emission cross section measurements with a 3090100100003 14 MeV neutron generator 3090100100004 AUTHOR (K.Gul, M.Anwar, S.M.Saleem, M.Ahmad) 3090100100005 INSTITUTE (3PAKNIL) 3090100100006 REFERENCE (J,NIM/B,24-25,496,1987) 3090100100007 ((J,RE,93,189,1986)=(C,85SANTA,1,525,1985)) Data for Al3090100100008 (C,86DUBROV,,285,1986) Brief report. Data for Pb and Cu3090100100009 FACILITY (CCW,3PAKNIL) 3090100100010 SAMPLE Natural targets each of 5.1 cm diameter and 5.1 cm long3090100100011 INC-SOURCE (D-T) Using 120 keV deuterons 3090100100012 DETECTOR (SCIN) NE213 liquid scintillator of 12.7 cm diameter 3090100100013 and 12.7 thickness was coupled to XP1040 PHM The bias 3090100100014 of the detector was set at 2 MeV neutron energy 3090100100015 METHOD (TOF,ASSOP) Flight path of 2.3 m forward of 90 degrees 3090100100016 and 3.3 m beyond 90 degrees. 3090100100017 ANALYSIS (INTED) The original measured double differential 3090100100018 U-emission data are not available but only some 3090100100019 integrated results, integrated in the E-range 3090100100020 6 to 11 MeV 3090100100021 CORRECTION Flux attenuation corrections for incident and exit 3090100100022 channels as well as those for in-scattering were 3090100100023 computed on the basis of monte carlo. 3090100100024 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 3090100100025 STATUS (TABLE) Table 1 of Nucl.Intr.Meth.B, 24-25 (1987) 496 3090100100026 HISTORY (19880712C) VOF 3090100100027 (19890213A) VOF.-Reaction codes were corrected. 3090100100028 (19890328A) VOF.-Analysis code added in sub. 5,6 and 7.3090100100029 (20090912A) SD: Updated to new date formats,lower case.3090100100030 (20220203U) VT REFERENCE: Vol. 24/25 -> 24-25 3090100100031 ENDBIB 29 0 3090100100032 COMMON 1 3 3090100100033 EN 3090100100034 MEV 3090100100035 14.6 3090100100036 ENDCOMMON 3 0 3090100100037 ENDSUBENT 36 0 3090100199999 SUBENT 30901002 20090912 31413090100200001 BIB 2 7 3090100200002 REACTION 1(13-AL-27(N,X)0-NN-1,EM,SIG) 3090100200003 2(13-AL-27(N,X)0-NN-1,EM,SIG) 3090100200004 ANALYSIS 1Obtained by integration of double differential 3090100200005 range. 3090100200006 2Obtained by adding the angle integrated cross 3090100200007 sections for each 1MeV energy bin lying in the 3090100200008 6-11 MeV energy range. 3090100200009 ENDBIB 7 0 3090100200010 NOCOMMON 0 0 3090100200011 DATA 4 1 3090100200012 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 3090100200013 MB MB MB MB 3090100200014 196.0 17.0 195.0 18.0 3090100200015 ENDDATA 3 0 3090100200016 ENDSUBENT 15 0 3090100299999 SUBENT 30901003 20090912 31413090100300001 BIB 2 8 3090100300002 REACTION 1(29-CU-63(N,X)0-NN-1,EM,SIG) 3090100300003 2(29-CU-63(N,X)0-NN-1,EM,SIG) 3090100300004 ANALYSIS 1Obtained by integration double differential 3090100300005 cross section data at each angle in the 6-11 MeV 3090100300006 range. 3090100300007 2Obtained by adding the angle integrated cross 3090100300008 sections for each 1MeV energy bin lying in the 3090100300009 6-11 MeV energy range. 3090100300010 ENDBIB 8 0 3090100300011 NOCOMMON 0 0 3090100300012 DATA 4 1 3090100300013 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 3090100300014 MB MB MB MB 3090100300015 198.0 10.0 194.0 11.0 3090100300016 ENDDATA 3 0 3090100300017 ENDSUBENT 16 0 3090100399999 SUBENT 30901004 20090912 31413090100400001 BIB 2 8 3090100400002 REACTION 1(82-PB-207(N,X)0-NN-1,EM,SIG) 3090100400003 2(82-PB-207(N,X)0-NN-1,EM,SIG) 3090100400004 ANALYSIS 1Obtained by integration double differential 3090100400005 cross section data at each angle in the 6-11 MeV 3090100400006 range. 3090100400007 2Obtained by adding the angle integrated cross 3090100400008 sections for each 1MeV energy bin lying in the 3090100400009 6-11 MeV energy range. 3090100400010 ENDBIB 8 0 3090100400011 NOCOMMON 0 0 3090100400012 DATA 4 1 3090100400013 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 3090100400014 MB MB MB MB 3090100400015 306.0 16.0 276.0 17.0 3090100400016 ENDDATA 3 0 3090100400017 ENDSUBENT 16 0 3090100499999 SUBENT 30901005 20090912 31413090100500001 BIB 2 8 3090100500002 REACTION (13-AL-27(N,X)0-NN-1,EM,DA,,LEG/RSL) 3090100500003 ANALYSIS (INTED) For obtaining angular distribution information,3090100500004 double differential cross section data were 3090100500005 integrated at each angle in the 6-11 MeV 3090100500006 energy range and then the angle integrated 3090100500007 value was obtained through Legendre polynomial 3090100500008 least squares fit using: 3090100500009 sigma(O)=(sig/4Pi)*(1+3*a1*P1+5*a2*P2) 3090100500010 ENDBIB 8 0 3090100500011 NOCOMMON 0 0 3090100500012 DATA 3 2 3090100500013 NUMBER DATA DATA-ERR 3090100500014 NO-DIM NO-DIM NO-DIM 3090100500015 1. 0.10 0.08 3090100500016 2. 0.07 0.05 3090100500017 ENDDATA 4 0 3090100500018 ENDSUBENT 17 0 3090100599999 SUBENT 30901006 20090912 31413090100600001 BIB 2 8 3090100600002 REACTION (29-CU-63(N,X)0-NN-1,EM,DA,,LEG/RSL) 3090100600003 ANALYSIS (INTED) For obtaining angular distribution information,3090100600004 double differential cross section data were 3090100600005 integrated at each angle in the 6-11 MeV 3090100600006 energy range and then the angle integrated 3090100600007 value was obtained through Legendre polynomial 3090100600008 least squares fit using: 3090100600009 sigma(O)=(sig/4Pi)*(1+3*a1*P1+5*a2*P2) 3090100600010 ENDBIB 8 0 3090100600011 NOCOMMON 0 0 3090100600012 DATA 3 2 3090100600013 NUMBER DATA DATA-ERR 3090100600014 NO-DIM NO-DIM NO-DIM 3090100600015 1. 0.13 0.03 3090100600016 2. 0.04 0.03 3090100600017 ENDDATA 4 0 3090100600018 ENDSUBENT 17 0 3090100699999 SUBENT 30901007 20090912 31413090100700001 BIB 2 8 3090100700002 REACTION (82-PB-207(N,X)0-NN-1,EM,DA,,LEG/RSL) 3090100700003 ANALYSIS (INTED) For obtaining angular distribution information,3090100700004 double differential cross section data were 3090100700005 integrated at each angle in the 6-11 MeV 3090100700006 energy range and then the angle integrated 3090100700007 value was obtained through Legendre polynomial 3090100700008 least squares fit using: 3090100700009 sigma(O)=(sig/4Pi)*(1+3*a1*P1+5*a2*P2) 3090100700010 ENDBIB 8 0 3090100700011 NOCOMMON 0 0 3090100700012 DATA 3 2 3090100700013 NUMBER DATA DATA-ERR 3090100700014 NO-DIM NO-DIM NO-DIM 3090100700015 1. 0.18 0.02 3090100700016 2. 0.04 0.03 3090100700017 ENDDATA 4 0 3090100700018 ENDSUBENT 17 0 3090100799999 ENDENTRY 7 0 3090199999999