ENTRY 23524 20190604 228023524 0 1 SUBENT 23524001 20190603 228023524 1 1 BIB 13 27 23524 1 2 TITLE The use of cobalt as an accurate thermal neutron flux 23524 1 3 monitor 23524 1 4 AUTHOR (N.K.Taylor, J.K.Linacre) 23524 1 5 REFERENCE (R,AERE-R-4111,1964) 23524 1 6 INSTITUTE (2UK HAR) 23524 1 7 FACILITY (REAC,2UK HAR) GLEEP and BEPO reactors 23524 1 8 INC-SPECT GLEEP: 23524 1 9 Cd ratio for Au was determined to be 2.17+-0.03. 23524 1 10 Ratio of thermal to total neutron density 0.942 was 23524 1 11 determined; using value 0.974 of Littler, the mean 23524 1 12 average is 0.958 . 23524 1 13 . Neutron spectra in GLEEP and BEPO are probaly 23524 1 14 sufficiently similar ( authors comment on page 20 ). 23524 1 15 SAMPLE . GLEEP: 23524 1 16 Four Au foils of ~1.8 mg/cm2 thickness, ~1 cm2 area. 23524 1 17 Samples 1 and 2 were irradiated without Cd, 23524 1 18 3 and 4 - with 1 mm thick Cd cover at the same 23524 1 19 position. 23524 1 20 DETECTOR (GEMUC) .with 7 mg/cm2 window, for beta-counting of Au.23524 1 21 RaD standard source was counted periodically during 23524 1 22 foil counting. 23524 1 23 METHOD (ACTIV) 23524 1 24 DECAY-DATA (27-CO-60-G,5.23YR) 23524 1 25 (79-AU-198-G,2.7D) 23524 1 26 CORRECTION For paralysis, background, decay. 23524 1 27 ADD-RES Self-shielding factors. 23524 1 28 HISTORY (20190604C) M.M. 23524 1 29 ENDBIB 27 0 23524 1 30 NOCOMMON 0 0 23524 1 31 ENDSUBENT 30 0 23524 199999 SUBENT 23524002 20190604 228023524 2 1 BIB 6 44 23524 2 2 REACTION 1(27-CO-59(N,X)27-CO-60,,SIG,,MXW) 23524 2 3 2(27-CO-59(N,X)27-CO-60,,SIG,,MXW) 23524 2 4 3(27-CO-59(N,X)27-CO-60,,SIG,,MXW) 23524 2 5 SAMPLE . BEPO: 23524 2 6 The same Au as at GLEEP 23524 2 7 Co wire of 0.010 inch diameter. 23524 2 8 DETECTOR (SCIN) Sodium iodine scintillation counter for gamma 23524 2 9 radiation of Co wires. Standard Co sources were used 23524 2 10 for calibration. 23524 2 11 METHOD 1 Experiment 1 23524 2 12 Cd ratio for Au 2.28 23524 2 13 Cd ratio for Co 15.5 23524 2 14 Bare Au foil activity,count/min/mg 4.937E+5 23524 2 15 Thermal Au foil activity,count/min/mg 2.770E+5 23524 2 16 Westcott thermal dose,n/cm2 2.388E+15 23524 2 17 Co sample activity,microCurie 0.0951 23524 2 18 Thermal Co sample activity,microCurie 0.0890 23524 2 19 2 Experiment 2 23524 2 20 Cd ratio for Au 2.33 23524 2 21 Cd ratio for Co 16.5 23524 2 22 Bare Au foil activity,count/min/mg 4.495E+5 23524 2 23 Thermal Au foil activity,count/min/mg 2.567E+5 23524 2 24 Westcott thermal dose,n/cm2 2.213E+15 23524 2 25 Co sample activity,microCurie 0.0935 23524 2 26 Thermal Co sample activity,microCurie 0.0880 23524 2 27 3 Experiment 3 23524 2 28 Cd ratio for Au 2.32 23524 2 29 Cd ratio for Co 16.5 23524 2 30 Bare Au foil activity,count/min/mg 4.449E+5 23524 2 31 Thermal Au foil activity,count/min/mg 2.531E+5 23524 2 32 Westcott thermal dose,n/cm2 2.182E+15 23524 2 33 Co sample activity,microCurie 0.0867 23524 2 34 Thermal Co sample activity,microCurie 0.0814 23524 2 35 ERR-ANALYS (DATA-ERR) Includes counting errors and manipulation of23524 2 36 data. 23524 2 37 (ERR-1) Cd ratio for Au 23524 2 38 (ERR-2) Cd ratio for Co 23524 2 39 (ERR-3) Bare Au foil activity at Co irradiation 23524 2 40 position 23524 2 41 (ERR-4) Thermal Au foil activity at Co irradiation 23524 2 42 position 23524 2 43 (ERR-5) Co sample activity 23524 2 44 (ERR-6) Co sample thermal neutron induced activity 23524 2 45 STATUS (TABLE) Table VI of Rep.AERE-R-4111,1964 23524 2 46 ENDBIB 44 0 23524 2 47 COMMON 5 3 23524 2 48 EN-DUMMY ERR-1 ERR-2 ERR-3 DATA-ERR 23524 2 49 EV PER-CENT PER-CENT PER-CENT PER-CENT 23524 2 50 0.0253 1.4 1.7 1.7 2.2 23524 2 51 ENDCOMMON 3 0 23524 2 52 DATA 6 1 23524 2 53 DATA 1DATA 2DATA 3ERR-4 ERR-5 ERR-6 23524 2 54 B B B PER-CENT PER-CENT PER-CENT 23524 2 55 32.69 34.18 32.66 1.7 1. 1.2 23524 2 56 ENDDATA 3 0 23524 2 57 ENDSUBENT 56 0 23524 299999 SUBENT 23524003 20190604 228023524 3 1 BIB 4 8 23524 3 2 REACTION (27-CO-59(N,X)27-CO-60,,SIG,,MXW) 23524 3 3 ANALYSIS Mean value for 3 experiments 23524 3 4 ERR-ANALYS (ERR-T) Total error 23524 3 5 (ERR-1) Counting and manipulation data 23524 3 6 (ERR-2) GLEEP calibration 23524 3 7 (ERR-3) Standard Co sources 23524 3 8 STATUS (TABLE) Table VI of Rep.AERE-R-4111,1964 23524 3 9 (DEP,23524002) Data of experiments 1-3 . 23524 3 10 ENDBIB 8 0 23524 3 11 COMMON 1 3 23524 3 12 EN-DUMMY 23524 3 13 EV 23524 3 14 0.0253 23524 3 15 ENDCOMMON 3 0 23524 3 16 DATA 6 1 23524 3 17 DATA ERR-T ERR-T ERR-1 ERR-2 ERR-3 23524 3 18 B B PER-CENT PER-CENT PER-CENT PER-CENT 23524 3 19 33.2 1.7 5.1 2.2 3.2 4. 23524 3 20 ENDDATA 3 0 23524 3 21 ENDSUBENT 20 0 23524 399999 SUBENT 23524004 20190604 228023524 4 1 BIB 6 17 23524 4 2 REACTION (27-CO-59(N,X)27-CO-60,,SIG,,MXW) 23524 4 3 SAMPLE . BEPO: 23524 4 4 Co-Al alloys: 23524 4 5 1 - 0.099 % Co, 0.050 inch diameter, 23524 4 6 2 - 0.745 % Co, 0.026 inch diameter; 23524 4 7 Accuracy of content +-2.% . 23524 4 8 Pure Co of 0.010 inch diameter. 23524 4 9 METHOD Irradiation time 24 hr or 50 hr at E6 hole of BEPO. 23524 4 10 Cooling time 3-4 weeks. 23524 4 11 Cd ratios - 9.27 for Co-Al alloy of 0.745%, 106 for 23524 4 12 Co-Al alloy 0.099%, 16.3 for 0.010 in diameter Co wire.23524 4 13 DETECTOR (SCIN) Sodium iodine scintillation counter for gamma 23524 4 14 radiation of Co wires. Standard Co sources were used 23524 4 15 for calibration. 23524 4 16 FLAG (1.) 0.745% alloy 23524 4 17 (2.) 0.099% alloy 23524 4 18 STATUS (TABLE) Text,page 11 of Rep.AERE-R-4111,1964 23524 4 19 ENDBIB 17 0 23524 4 20 COMMON 1 3 23524 4 21 EN-DUMMY 23524 4 22 EV 23524 4 23 0.0253 23524 4 24 ENDCOMMON 3 0 23524 4 25 DATA 2 2 23524 4 26 DATA FLAG 23524 4 27 B NO-DIM 23524 4 28 37.5 1. 23524 4 29 36.5 2. 23524 4 30 ENDDATA 4 0 23524 4 31 ENDSUBENT 30 0 23524 499999 SUBENT 23524005 20190604 228023524 5 1 BIB 4 5 23524 5 2 REACTION (27-CO-59(N,X)27-CO-60,,SIG,,SPA) 23524 5 3 ANALYSIS Bare sample activation cross section. 23524 5 4 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 23524 5 5 article. 23524 5 6 STATUS (TABLE) Text, page 18 of Rep.AERE-R-4111,1964 23524 5 7 ENDBIB 5 0 23524 5 8 COMMON 1 3 23524 5 9 EN-DUMMY 23524 5 10 EV 23524 5 11 0.0253 23524 5 12 ENDCOMMON 3 0 23524 5 13 DATA 2 1 23524 5 14 DATA DATA-ERR 23524 5 15 B B 23524 5 16 36.3 1.5 23524 5 17 ENDDATA 3 0 23524 5 18 ENDSUBENT 17 0 23524 599999 ENDENTRY 5 0 2352499999999