ENTRY 30674 20090923 31403067400000001 SUBENT 30674001 20090923 31403067400100001 BIB 10 19 3067400100002 INSTITUTE (3BULSOF) 3067400100003 (3BULBUL) Third author 3067400100004 (3BULBLA) Last author 3067400100005 REFERENCE (J,BJP,10,(6),601,1983) 3067400100006 AUTHOR (A.Antov,E.Dobreva,I.Ephtimov,N.Nenoff,N.Stancheva) 3067400100007 TITLE On the determination of reaction cross-sections for 3067400100008 14 MeV neutrons 3067400100009 FACILITY (CCW,3BULBLA) 3067400100010 INC-SOURCE (D-T) solid Ti-T sample. 3067400100011 Neutron flux was (1-2)x10**9 n/cm2/s 3067400100012 METHOD (STTA,ACTIV) 3067400100013 (MOMIX) samples and monitor mixed homogeneously 3067400100014 DETECTOR (GELI) 40 cm3 coaxial Ge(Li) dector 2.2keV resolution 3067400100015 at 1332keV 3067400100016 STATUS (TABLE) Data taken from 3067400100017 J.Bulg.J.Phys,10,(6),(1983),601. 3067400100018 HISTORY (19840409C) DG.- 3067400100019 (20090914A) SD:Updated to new date formats,lower case. 3067400100020 OS. Subentry 6 added, BIB sections rearranged. 3067400100021 ENDBIB 19 0 3067400100022 COMMON 1 3 3067400100023 EN 3067400100024 MEV 3067400100025 1.4540E+01 3067400100026 ENDCOMMON 3 0 3067400100027 ENDSUBENT 26 0 3067400199999 SUBENT 30674002 20090903 31403067400200001 BIB 6 24 3067400200002 REACTION (66-DY-162(N,P)65-TB-162,,SIG) 3067400200003 SAMPLE Dy(2)-O(3) and Fe(2)-O(3) mixed homogeneously 3067400200004 Samples were prepared with different Dy to Fe ratios 3067400200005 and weights of 200 and 500 mg, respectively. 3067400200006 DECAY-DATA (65-TB-162,7.76MIN,DG,260.,0.8,DG,807.,0.43) 3067400200007 MONITOR (26-FE-56(N,P)25-MN-56,,SIG) 3067400200008 Monitor cross section value obtained as result of 3067400200009 Fe-56(n,p)/Al-27(n,a) measurement at 14.54 MeV and 3067400200010 interpolation with the results of Ryves and Kolkowski 3067400200011 for Fe-56(n,p) at 14.68 MeV and of Friedmann for 3067400200012 Al-27(n,a) at 14.42 MeV. 3067400200013 DECAY-MON (25-MN-56,2.58HR,DG,847.,0.988) 3067400200014 ERR-ANALYS (DATA-ERR) Following uncertainties were 3067400200015 taken into account: 3067400200016 -Neutron flux monitor in reaction cross section 3067400200017 -Gamma-ray peak areas 3067400200018 -Detector efficiency calibration 3067400200019 -Self-absorption in the samples 3067400200020 The uncertainties in the sample weight determination 3067400200021 and those due to mixing of the monitor and samples 3067400200022 were negligible. 3067400200023 Error due to uncertainties in the decay characteristics3067400200024 of the investigated nuclides were not taken into 3067400200025 account. 3067400200026 ENDBIB 24 0 3067400200027 NOCOMMON 0 0 3067400200028 DATA 4 1 3067400200029 MONIT MONIT-ERR DATA DATA-ERR 3067400200030 MB MB MB MB 3067400200031 1.1090E+02 2.8000E+00 4.0500E+00 2.4000E-01 3067400200032 ENDDATA 3 0 3067400200033 ENDSUBENT 32 0 3067400299999 SUBENT 30674003 20090923 31403067400300001 BIB 6 25 3067400300002 REACTION (70-YB-174(N,P)69-TM-174,,SIG) 3067400300003 SAMPLE Yb(2)-O(3) and Fe(2)-O(3) mixed homogeneously 3067400300004 Samples were prepared with different Yb to Fe ratios 3067400300005 and weight of 200 and 500 mg, respectively 3067400300006 DECAY-DATA (69-TM-174,5.4MIN,DG,273.,0.887,DG,366.,0.954, 3067400300007 DG,992.,0.9) 3067400300008 MONITOR (26-FE-56(N,P)25-MN-56,,SIG) 3067400300009 Monitor cross-section value obtained as result of 3067400300010 Fe-56(n,p)/Al-27(n,a) measurement at 14.54 MeV and 3067400300011 interpolation with the results of Ryves and Kolowski 3067400300012 for Fe-56(n,p) at 14.68 MeV and of Friedmann for 3067400300013 Al-27(n,a) at 14.42 MeV. 3067400300014 DECAY-MON (25-MN-56,2.58HR,DG,847.,0.988) 3067400300015 ERR-ANALYS (DATA-ERR) Following uncertainties were 3067400300016 taken into account: 3067400300017 -Neutron flux monitor in reaction cross section 3067400300018 -Gamma-ray peak areas 3067400300019 -Detector efficiency calibration 3067400300020 -Self-absorption in the samples 3067400300021 The uncertainties in the sample weight determination 3067400300022 and those due to mixing of the monitor and samples 3067400300023 were negligible. 3067400300024 Error due to uncertainties in the decay characteristics3067400300025 of the investigated nuclides were not taken into 3067400300026 account. 3067400300027 ENDBIB 25 0 3067400300028 NOCOMMON 0 0 3067400300029 DATA 4 1 3067400300030 MONIT MONIT-ERR DATA DATA-ERR 3067400300031 MB MB MB MB 3067400300032 1.1090E+02 2.8000E+00 2.7000E+00 1.6000E-01 3067400300033 ENDDATA 3 0 3067400300034 ENDSUBENT 33 0 3067400399999 SUBENT 30674004 20090903 31403067400400001 BIB 7 21 3067400400002 REACTION (70-YB-176(N,P)69-TM-176,,SIG) 3067400400003 SAMPLE 200 and 500 mg of Yb(2)-O(3) 3067400400004 DECAY-DATA (69-TM-176,1.9MIN,DG,190.,0.442,DG,1069.,0.33) 3067400400005 MONITOR (70-YB-174(N,P)69-TM-174,,SIG) 3067400400006 STATUS (DEP,30674003) The cross-section of monitor reaction 3067400400007 was determined in the present work. 3067400400008 See subentry 30674003. 3067400400009 DECAY-MON (69-TM-174,5.4MIN,DG,273.,0.887,DG,366.,0.954, 3067400400010 DG,992.,0.9) 3067400400011 ERR-ANALYS (DATA-ERR) Following uncertainties were 3067400400012 taken into account: 3067400400013 -Neutron flux monitor in reaction cross section 3067400400014 -Gamma-ray peak areas 3067400400015 -Detector efficiency calibration 3067400400016 -Self-absorption in the samples 3067400400017 The uncertainties in the sample weight determination 3067400400018 and those due to mixing of the monitor and samples 3067400400019 were negligible. 3067400400020 Error due to uncertainties in the decay characteristics3067400400021 of the investigated nuclides were not taken into 3067400400022 account. 3067400400023 ENDBIB 21 0 3067400400024 NOCOMMON 0 0 3067400400025 DATA 4 1 3067400400026 MONIT MONIT-ERR DATA DATA-ERR 3067400400027 MB MB MB MB 3067400400028 2.7000E+00 1.6000E-01 1.8000E+00 2.0000E-01 3067400400029 ENDDATA 3 0 3067400400030 ENDSUBENT 29 0 3067400499999 SUBENT 30674005 20090903 31403067400500001 BIB 7 21 3067400500002 REACTION (70-YB-176(N,A)68-ER-173,,SIG) 3067400500003 SAMPLE 200 and 500 mgr of Yb(2)-O(3) 3067400500004 DECAY-DATA (68-ER-173,1.4MIN,DG,199.,0.48,DG,895.,0.538) 3067400500005 MONITOR (70-YB-174(N,P)69-TM-174,,SIG) 3067400500006 STATUS (DEP,30674003) The cross-section of monitor reaction 3067400500007 was determined in the present work. 3067400500008 See subentry 30674003. 3067400500009 DECAY-MON (69-TM-174,5.4MIN,DG,273.,0.887,DG,366.,0.954, 3067400500010 DG,992.,0.9) 3067400500011 ERR-ANALYS (DATA-ERR) Following uncertainties were 3067400500012 taken into account: 3067400500013 -Neutron flux monitor in reaction cross section 3067400500014 -Gamma-ray peak areas 3067400500015 -Detector efficiency calibration 3067400500016 -Self-absorption in the samples 3067400500017 The uncertainties in the sample weight determination 3067400500018 and those due to mixing of the monitor and samples 3067400500019 were negligible. 3067400500020 Error due to uncertainties in the decay characteristics3067400500021 of the investigated nuclides were not taken into 3067400500022 account. 3067400500023 ENDBIB 21 0 3067400500024 NOCOMMON 0 0 3067400500025 DATA 4 1 3067400500026 MONIT MONIT-ERR DATA DATA-ERR 3067400500027 MB MB MB MB 3067400500028 2.7000E+00 1.6000E-01 7.0000E-01 2.0000E-01 3067400500029 ENDDATA 3 0 3067400500030 ENDSUBENT 29 0 3067400599999 SUBENT 30674006 20090903 31403067400600001 BIB 6 20 3067400600002 REACTION ((26-FE-56(N,P)25-MN-56,,SIG)/ 3067400600003 (13-AL-27(N,A)11-NA-24,,SIG)) 3067400600004 DECAY-DATA (25-MN-56,2.58HR,DG,847.,0.988) 3067400600005 (11-NA-24,14.96HR,DG,1369.,1.00) 3067400600006 ADD-RES Using the Fe-56(n,p)/Al-27(n,a) ratio value obtained in3067400600007 the present work and the results of Ryves and Kolkowski3067400600008 (J.Phys.G.6(1980)771) for the Fe-56(n,p) cross-section3067400600009 at 14.68 MeV and of Friedmann(z.Phys.A302(1981)271) for3067400600010 the Al-27(n,a) cross-section at 14.42 MeV authors of 3067400600011 the present work have redetermined the cross-section 3067400600012 for Fe-56(n,p) and Al(n,a) at 14.54 MeV. 3067400600013 The interpolation resulted in 110.9 +- 2.8 mb and 3067400600014 115.4 +- 2.9 mb respectively. 3067400600015 STATUS (TABLE)Data taken from Bul.J.Phys.10,(6),(1983),601. 3067400600016 ERR-ANALYS (DATA-ERR) Following uncertainties were taken 3067400600017 into account: 3067400600018 (ERR-1,0.6,0.9) Peak area determination 0.6 - 0.9% 3067400600019 * efficiency calibration for 846.8 keV 1.7% 3067400600020 for 1368.6 keV 2.2% 3067400600021 HISTORY (20090914C) OS. Subentry added, moved from entry 30675.3067400600022 ENDBIB 20 0 3067400600023 NOCOMMON 0 0 3067400600024 DATA 2 1 3067400600025 DATA DATA-ERR 3067400600026 NO-DIM NO-DIM 3067400600027 9.6100E-01 2.3000E-02 3067400600028 ENDDATA 3 0 3067400600029 ENDSUBENT 28 0 3067400699999 ENDENTRY 6 0 3067499999999