ENTRY 32503 20101206 31473250300000001 SUBENT 32503001 20101206 31473250300100001 BIB 15 56 3250300100002 TITLE Measurement of inelastic cross sections for the 3250300100003 reaction Sr-87(n,inl)Sr-87m 3250300100004 AUTHOR (Song Linggen,Wu Songmao,Xu Zhizheng,You Junsheng, 3250300100005 Wu Zhihua) 3250300100006 INSTITUTE (3CPRFUD) 3250300100007 REFERENCE (J,CNP,7,(1),58,1985) in Chinese 3250300100008 (C,88MITO,,315,198803) 3250300100009 FACILITY (VDG,3CPRFUD) 3250300100010 INC-SOURCE (P-T) For En=0.9-1.8 MeV, solid Ti-T target(mass of 3250300100011 Ti=0.4-1.6 milli-g/cm2) 3250300100012 (D-D) for En=3.2-5.7 MeV, solid Ti-D target(mass of 3250300100013 Ti=0.51-1.17 milli-g/cm2) 3250300100014 METHOD (ACTIV) 3250300100015 MONITOR Absolute measurement, a recoil proton telescope semi- 3250300100016 conductor detector used for neutron flux absolute 3250300100017 measurement in En=0.9-1.8 MeV energy range, and a 3250300100018 calibrated BF3 neutron counter used for En=3.2-5.7 MeV 3250300100019 energy range 3250300100020 SAMPLE Isotopic sample, abundance of Sr-87 was 52-64%. 3250300100021 Sr(NO3)2 powder was pressed as thin plate, and enclosed3250300100022 in a polyvinyl film, the sample diameter=11 mm, 3250300100023 weight=270-480 milli-gram 3250300100024 DETECTOR (NAICR) A known efficiency NaI(Tl) detector(diameter=7.3250300100025 6 cm, length=7.6 cm) used for gamma-ray measurement. 3250300100026 PART-DET (DG) 3250300100027 CORRECTION Corrections are performed for 3250300100028 . self-absorption in sample 3250300100029 . interference reaction for Sr-86(n,gamma)Sr-87-m 3250300100030 . scattering neutron from room-wall and others 3250300100031 . neutron flux attenuation in cadmium box(when irradia-3250300100032 ted, the sample was put into a cadmium box) 3250300100033 ERR-ANALYS (ERR-T) Main error sources as follows 3250300100034 . neutron flux measurement: 3250300100035 (ERR-1) 5.0% for BF3 neutron counter 3250300100036 (ERR-2) 3.0% for recoil proton telescope and 3250300100037 semiconductor detector 3250300100038 (ERR-3) 6.0% for full energy peak efficiency of 3250300100039 NaI(Tl) detector 3250300100040 (ERR-4,2.0,3.0) due to correction for room-wall 3250300100041 scattering neutrons 3250300100042 (ERR-5) 1.5% due to correction for scattering neutrons 3250300100043 from cadmium box and source target material3250300100044 (ERR-6) 0.5% due to correction for interference 3250300100045 reaction 3250300100046 (ERR-7) 0.1% for sample weight 3250300100047 (ERR-8) 0.1% for isotopic abundance 3250300100048 (ERR-9) 1.0% due to correction for self-absorption 3250300100049 (ERR-10) 0.1% due to dead time for flux monitor 3250300100050 (ERR-11,0.5,4.0) due to statistical for gamma 3250300100051 counting 3250300100052 (ERR-12) 2.0 due to geometry 3250300100053 STATUS (TABLE) Data taken from Table 1 of Chinese J. of Nucl. 3250300100054 Physics,7(1),58,1988. 3250300100055 HISTORY (19891020C) Compiled by Liang Qichang at CNDC 3250300100056 (20100930A) SD:Updated to new date formats,lower case. 3250300100057 Cosmetic changes 3250300100058 ENDBIB 56 0 3250300100059 COMMON 10 6 3250300100060 ERR-1 ERR-2 ERR-3 ERR-5 ERR-6 ERR-7 3250300100061 ERR-8 ERR-9 ERR-10 ERR-12 3250300100062 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3250300100063 PER-CENT PER-CENT PER-CENT PER-CENT 3250300100064 5. 3. 6. 1.5 0.5 0.1 3250300100065 0.1 1. 0.1 2. 3250300100066 ENDCOMMON 6 0 3250300100067 ENDSUBENT 66 0 3250300199999 SUBENT 32503002 20100315 31473250300200001 BIB 2 3 3250300200002 REACTION (38-SR-87(N,INL)38-SR-87-M,,SIG) 3250300200003 HISTORY (19900523A) VOF.-Data corrected according to the 3250300200004 author's communication. 3250300200005 ENDBIB 3 0 3250300200006 NOCOMMON 0 0 3250300200007 DATA 4 13 3250300200008 EN EN-ERR DATA DATA-ERR 3250300200009 MEV MEV MB MB 3250300200010 0.975 0.0223 32.4900 3.940 3250300200011 1.182 0.0214 84.7900 9.360 3250300200012 1.330 0.0770 100.38 10.94 3250300200013 1.538 0.0726 144.12 16.00 3250300200014 1.747 0.0660 205.67 22.50 3250300200015 3.23 0.133 285.75 27.86 3250300200016 3.40 0.112 241.38 24.74 3250300200017 3.82 0.077 184.25 18.83 3250300200018 4.12 0.137 167.31 17.08 3250300200019 4.49 0.111 154.05 15.76 3250300200020 4.83 0.095 115.48 11.93 3250300200021 5.16 0.087 167.93 17.13 3250300200022 5.69 0.071 129.08 13.17 3250300200023 ENDDATA 15 0 3250300200024 ENDSUBENT 23 0 3250300299999 ENDENTRY 2 0 3250399999999