ENTRY 40135 20150109 41724013500000001 SUBENT 40135001 20150109 41724013500100001 BIB 17 63 4013500100002 TITLE Excitation functions for the reactions 4013500100003 Al-27(n,alpha)Na-24 and Al-27(n,p)Mg-27 4013500100004 AUTHOR (Yu.A.Nemilov,Yu.N.Trofimov) 4013500100005 INSTITUTE (4RUSRI) 4013500100006 REFERENCE (R,INDC(CCP)-42,13,1974) English transl. of 4013500100007 report YK-9,53 4013500100008 (R,YK-9,53,1972) Tables and graphs are given 4013500100009 (R,YFI-12,89,1971) Abstract given 4013500100010 (R,INDC(CCP)-030,78,1972) Engl.translation of YFI-12,894013500100011 MONITOR (92-U-238(N,F),,SIG) Fission cross section of U-238 4013500100012 was used for neutron flux. 4013500100013 REL-REF (R,A1120002,L.Cranberg+,J,PR,104,1639,1956) - data for 4013500100014 correction for the neutron background 4013500100015 METHOD (ACTIV) Activation 4013500100016 Irradiation time 0.5 - 1.5 hr. 4013500100017 FACILITY (CYCLO,4RUSRI) Cyclotron 4013500100018 DETECTOR (PROPC) 4PI proportional gas-flow counter filled with 4013500100019 methane 4013500100020 (IOCH) The fast neutron flux was measured using an 4013500100021 ionization fission chamber with a U-238 layer. The 4013500100022 amount of uranium in the chamber was found by 4013500100023 alpha-counting 4013500100024 INC-SOURCE (D-D) Deuteron-deuterium reaction. 4013500100025 Deuteron energy 6.6 MeV. 4013500100026 PART-DET (B-) Decay beta- electrons 4013500100027 SAMPLE Metallic disks 10 mm in diameter and 0.1 mm 4013500100028 in width 4013500100029 Samples were placed at 45 mm distance from the centre 4013500100030 of neutron source. 4013500100031 CORRECTION At the determination of the flux of neutrons were 4013500100032 introduced correction for background of scattered 4013500100033 neutrons 10-60% and correction for neutrons from 4013500100034 break-up of deuterons 5% . 4013500100035 Correction for the counting of the fission from the 4013500100036 latter neutrons was 5+-1%. 4013500100037 Correction for the counting of the fission was 5+-1% 4013500100038 ERR-ANALYS (EN-ERR) Uncertainty in the energy was conditioned by4013500100039 breaking of deuterons in target and different angles 4013500100040 of neutron escape 4013500100041 (ERR-T) Square root total error arising from : 4013500100042 (ERR-1) Uncertainty of the weight of U-238 1.5% 4013500100043 (MONIT-ERR) Error of fission cross section U-238 3.% 4013500100044 (ERR-2) Error of the counting of fission 2.% 4013500100045 (ERR-3) Error in efficiency of activity counting 3% 4013500100046 (ERR-4) Uncertainty in the background of neutrons 3% 4013500100047 (ERR-S) Error in the counting rate of the samples 1% 4013500100048 (ERR-5) Error in the geometry of the experiment 1% 4013500100049 COMMENT Specific activity were determined by extrapolation of 4013500100050 the sample to zero width 4013500100051 STATUS (TABLE) Table 1 from YK-9,53,1972 4013500100052 HISTORY (19730225C) Compiled at the centre 4013500100053 (19740920A) correction in common-section 4013500100054 (19860506U) some errors corrected 4013500100055 (20150109A) SD: Updated to new date formats,lower case.4013500100056 Corrections according last EXFOR rules and Dict. 4013500100057 Ref. on Engl.transl. of YK-9 added. BIB updated. 4013500100058 EN-ERR moved to Subent 1 from Subents 2,3. 4013500100059 (ERR-ANALYS, author's name; MONIT-REF -> REL-REF) 4013500100060 (20151020A) M.M. Articles were checked, BIB information4013500100061 was updated in AUTHOR, REFERENCE, SAMPLE, MONITOR, 4013500100062 INC-SOURCE. ERR-ANALYS was corrected: 4013500100063 ERR-S -> ERR-2, ERR-4 -> ERR-S, DATA-ERR -> ERR-4 , 4013500100064 ERR-2 -> MONIT-ERR . 4013500100065 ENDBIB 63 0 4013500100066 COMMON 8 6 4013500100067 ERR-1 MONIT-ERR ERR-2 ERR-3 ERR-4 ERR-S 4013500100068 EN-ERR ERR-5 4013500100069 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4013500100070 MEV PER-CENT 4013500100071 1.5 3. 2. 3. 3. 1. 4013500100072 0.3 1. 4013500100073 ENDCOMMON 6 0 4013500100074 ENDSUBENT 73 0 4013500199999 SUBENT 40135002 20150109 41724013500200001 BIB 1 1 4013500200002 REACTION (13-AL-27(N,A)11-NA-24,,SIG) (n,alpha) cross section 4013500200003 ENDBIB 1 0 4013500200004 NOCOMMON 0 0 4013500200005 DATA 3 4 4013500200006 EN DATA ERR-T 4013500200007 MEV MB MB 4013500200008 9.3 82. 6. 4013500200009 9.05 78. 7. 4013500200010 8.6 77. 8. 4013500200011 7.7 43. 5. 4013500200012 ENDDATA 6 0 4013500200013 ENDSUBENT 12 0 4013500299999 SUBENT 40135003 20150109 41724013500300001 BIB 1 1 4013500300002 REACTION (13-AL-27(N,P)12-MG-27,,SIG) (n,p) cross section 4013500300003 ENDBIB 1 0 4013500300004 NOCOMMON 0 0 4013500300005 DATA 3 4 4013500300006 EN DATA ERR-T 4013500300007 MEV MB MB 4013500300008 9.3 92. 8. 4013500300009 9.05 98. 9. 4013500300010 8.6 92. 10. 4013500300011 8.0 75. 8. 4013500300012 ENDDATA 6 0 4013500300013 ENDSUBENT 12 0 4013500399999 ENDENTRY 3 0 4013599999999