ENTRY 20755 20200906 22912075500000001 SUBENT 20755001 20200906 22912075500100001 BIB 15 35 2075500100002 TITLE Activation cross section of O-16, Si-28, Na-23, for 2075500100003 14.1+-0.3 MeV neutrons 2075500100004 AUTHOR (M.L.Sanchez,J.L.Casanova,J.Casanova) 2075500100005 REFERENCE (J,ARS,71,119,1975) in Spanish 2075500100006 (P,NEANDC(OR)-140,8,1974) from Spain (F.Manero ed.) 2075500100007 short description, data table. 2075500100008 INSTITUTE (2SPNVLD) 2075500100009 FACILITY (NGEN,2SPNVLD) Philips PW-5304 neutron generator. 2075500100010 INC-SOURCE (D-T) T(d,n)He-4 reaction produced with the neutron 2075500100011 generator 14.1+-0.3 MeV 2075500100012 INC-SPECT neutron flux of 10E+8 n/sec. 2075500100013 (EN-RSL-HW) Energy spread value 2075500100014 SAMPLE Cylinders,0.9 cm in diam.,6 cm long,constituted by 2075500100015 11-Na-23, 8-O-16, 14-Si-28. 2075500100016 METHOD (ACTIV) 2075500100017 Investigations have been carried out about flux 2075500100018 gradients inside the samples, because of their 2075500100019 thickness. 2075500100020 ANALYSIS Due to the short period of the observed element 2075500100021 decays authors used an accumulation method measuring 2075500100022 half-life. 2075500100023 ERR-ANALYS (ERR-S) Statistical error 2075500100024 DETECTOR (NAICR) 3" x 3" well type NaI(Tl) detector. 2075500100025 MONITOR (29-CU-63(N,2N)29-CU-62,,SIG) The Cu-63(n,2n)reaction 2075500100026 is used to obtain the mean neutron flux in the sample 2075500100027 (2.04E+4 n/cm2), to calibrate an anthracene 2075500100028 crystal detector, and to check the NaI(Tl) detector 2075500100029 efficiency. 2075500100030 The cross section of this reaction was assumed to 2075500100031 be 478+-48 millibarns for 14.1 MeV neutrons. 2075500100032 STATUS (TABLE) Tbl.III from Anal.Fis.Quim.,71(1975)119, iss.2 2075500100033 HISTORY (19771219C) 2075500100034 (19801112A) G.C., Reaction strings corrected. 2075500100035 (20200906A) SD:Updated to new date formats, lower case.2075500100036 Corrections in all Subents. EN-RSL -> EN-RSL-HW. 2075500100037 ENDBIB 35 0 2075500100038 COMMON 4 3 2075500100039 EN EN-RSL-HW MONIT MONIT-ERR 2075500100040 MEV MEV MB MB 2075500100041 14.1 0.3 478. 48. 2075500100042 ENDCOMMON 3 0 2075500100043 ENDSUBENT 42 0 2075500199999 SUBENT 20755002 20200906 22912075500200001 BIB 4 5 2075500200002 REACTION (8-O-16(N,P)7-N-16,,SIG) 2075500200003 DECAY-DATA (7-N-16,7.1SEC,DG,6130.,,DG,7120.) 2075500200004 COMMENT Method and analysis are given in Subent 001. 2075500200005 HISTORY (19801112A) G.C., Energy values moved to Subent 001. 2075500200006 (20200906A) SD: SF5=CN deleted from REACTION code. 2075500200007 ENDBIB 5 0 2075500200008 NOCOMMON 0 0 2075500200009 DATA 3 1 2075500200010 DATA ERR-S HL-ERR 2075500200011 MB MB SEC 2075500200012 259. 43. 0.2 2075500200013 ENDDATA 3 0 2075500200014 ENDSUBENT 13 0 2075500299999 SUBENT 20755003 20200906 22912075500300001 BIB 4 5 2075500300002 REACTION (11-NA-23(N,A)9-F-20,,SIG) 2075500300003 DECAY-DATA (9-F-20,12.5SEC,DG,1630.) 2075500300004 COMMENT Method and analysis are given in Subent 001. 2075500300005 HISTORY (19801112A) G.C., Energy values moved to Subent 001. 2075500300006 (20200906A) SD: SF5=CN deleted from REACTION code. 2075500300007 ENDBIB 5 0 2075500300008 NOCOMMON 0 0 2075500300009 DATA 3 1 2075500300010 DATA ERR-S HL-ERR 2075500300011 MB MB SEC 2075500300012 158. 28. 0.5 2075500300013 ENDDATA 3 0 2075500300014 ENDSUBENT 13 0 2075500399999 SUBENT 20755004 20200906 22912075500400001 BIB 4 5 2075500400002 REACTION (14-SI-28(N,P)13-AL-28,,SIG) 2075500400003 DECAY-DATA (13-AL-28,2.42MIN,DG,1780.) 2075500400004 COMMENT Method and analysis are given in Subent 001. 2075500400005 HISTORY (19801112A) G.C., Energy values moved to Subent 001. 2075500400006 (20200906A) SD: SF5=CN deleted from REACTION code. 2075500400007 ENDBIB 5 0 2075500400008 NOCOMMON 0 0 2075500400009 DATA 3 1 2075500400010 DATA ERR-S HL-ERR 2075500400011 MB MB MIN 2075500400012 38. 12. 0.15 2075500400013 ENDDATA 3 0 2075500400014 ENDSUBENT 13 0 2075500499999 ENDENTRY 4 0 2075599999999