ENTRY 20191 20211218 23062019100000001 SUBENT 20191001 20211218 23062019100100001 BIB 14 27 2019100100002 TITLE Average cross-sections of the S-32(n,p)p-32 and 2019100100003 Al-27(n,alpha)Na-24 reactions for fission neutrons 2019100100004 AUTHOR (H.Depuydt,M.Neve De Mevergnies) 2019100100005 INSTITUTE (2BLGMOL) 2019100100006 REFERENCE (J,JNE/AB,16,447,1962) 2019100100007 REL-REF (N,20229001,A.Fabry,J,NUK,10,280,1967) similar experim.2019100100008 FACILITY (REAC,2BLGMOL) BR-1 reactor, thermal column. 2019100100009 INC-SOURCE Enriched uranium fission plate. 2019100100010 INC-SPECT Fission spectrum from fission plate. 2019100100011 METHOD (ACTIV) 2019100100012 DETECTOR (GEMUC) Geiger counter 2019100100013 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 2019100100014 = 98.8 +- 0.3 barn, BNL-325, 2-nd ed. 2019100100015 (1958) For measuring the thermal neutron flux. 2019100100016 (92-U-0(N,F),,SIG) 2019100100017 Macroscopic cross-section of the fission- 2019100100018 plate = 23.8 +- 0.2 1/cm. 2019100100019 Fission neutron flux calculated using equation (2) of 2019100100020 J.Nuclear Energy A/B,16(1962)447. 2019100100021 ERR-ANALYS (ERR-T) Total error 2019100100022 (ERR-1) The error due to the inaccuracy of the thermal2019100100023 neutron data is assumed to be 1.1% 2019100100024 STATUS (TABLE) from the absract of 2019100100025 J.Nuclear Energy A/B,16(1962)447. 2019100100026 HISTORY (19721005C) 2019100100027 (20211218A) SD:Updated to new date formats,lower case. 2019100100028 Corrections according to MEMO CP-D/1028. 2019100100029 ENDBIB 27 0 2019100100030 COMMON 2 3 2019100100031 EN-DUMMY ERR-1 2019100100032 MEV PER-CENT 2019100100033 1.0 1.1 2019100100034 ENDCOMMON 3 0 2019100100035 ENDSUBENT 34 0 2019100199999 SUBENT 20191002 20211218 23062019100200001 BIB 4 7 2019100200002 REACTION (13-AL-27(N,A)11-NA-24,,SIG,,FIS) 2019100200003 DECAY-DATA (11-NA-24,15.050HR,B-) 2019100200004 SAMPLE A carefully weighed sample of spec-pure aluminium 2019100200005 metal, 1 cm dia. and 0.07 mm thickness, is enclosed 2019100200006 in a 1 mm thick cadmium box. 2019100200007 HISTORY (20211218A) SD: SF4=Na-24g -> Na-24 in REACTION code. 2019100200008 BIB updated. DATA-ERR -> ERR-T. 2019100200009 ENDBIB 7 0 2019100200010 NOCOMMON 0 0 2019100200011 DATA 2 1 2019100200012 DATA ERR-T 2019100200013 B B 2019100200014 6.2800E-04 3.1000E-05 2019100200015 ENDDATA 3 0 2019100200016 ENDSUBENT 15 0 2019100299999 SUBENT 20191003 20211218 23062019100300001 BIB 5 11 2019100300002 REACTION (16-S-32(N,P)15-P-32,,SIG,,FIS) 2019100300003 SAMPLE About O-1 g ammonium sulphate powder is put in an 2019100300004 aluminium cylinder of 1 cm dia., 0.1 cm depth, 0.02 2019100300005 cm wall thickness and having 6 u mylar film cover 2019100300006 (total weight of the film: ~10**(-4) g). The 2019100300007 cylinder is enclosed in a cadmium box. 2019100300008 DECAY-DATA (15-P-32,14.320D,B-) 2019100300009 ERR-ANALYS (ERR-2) The irradiation, calibration and counting 2019100300010 of the four sulphur samples produce on the average 2019100300011 activity a standard deviation of 2%. 2019100300012 HISTORY (20211218U) SD: BIB updated. DATA-ERR -> ERR-T. 2019100300013 ENDBIB 11 0 2019100300014 NOCOMMON 0 0 2019100300015 DATA 3 1 2019100300016 DATA ERR-2 ERR-T 2019100300017 B PER-CENT B 2019100300018 6.4500E-02 2. 2.8000E-03 2019100300019 ENDDATA 3 0 2019100300020 ENDSUBENT 19 0 2019100399999 ENDENTRY 3 0 2019199999999