ENTRY 23370 20180725 226923370 0 1 SUBENT 23370001 20180726 226923370 1 1 BIB 10 31 23370 1 2 AUTHOR (C.G.Campbell,R.G.Freemantle, M.J.Poole) 23370 1 3 TITLE Measurements of reactor spectra by time-of-flight and 23370 1 4 integral methods 23370 1 5 REFERENCE (C,58GENEVA,16,233,1958) 23370 1 6 INSTITUTE (2UK HAR) 23370 1 7 REL-REF (M,,M.J.Poole,J,JNE,5,325,1957) 23370 1 8 Pulse source method details and some results. 23370 1 9 (R,,C.G.Campbell+,R,AERE-RP/R-2031,1957) 23370 1 10 Thermal fission rate data, used for normalization. 23370 1 11 FACILITY (REAC,2UK HAR) BEPO reactor and NERO reactor, 23370 1 12 DIDO mockup in DIMPLE 23370 1 13 (OSCIP,2UK HAR) GLEEP oscillator 23370 1 14 (CRASS,2UK HAR) Sub-critical assemblies for spectrum 23370 1 15 work 23370 1 16 INC-SOURCE Light water moderated lattices. 23370 1 17 Graphite moderated lattices. 23370 1 18 Heavy water moderated lattices. 23370 1 19 Pure moderators 23370 1 20 METHOD (TOF) Pulsed source method: 23370 1 21 neutron spectrum was measured by TOF (12 m flight path)23370 1 22 Integral method: 23370 1 23 spectrum is assumed as sum of two components- 23370 1 24 Maxwellian distribution with temperature T and 23370 1 25 slowing down distribution with ratio epithermal to 23370 1 26 thermal neutron density. 23370 1 27 DETECTOR (FISCH) 1/4 inch diameter, 2 or 11 ft length. 23370 1 28 Containing U-233, U-235, Pu-239 . 23370 1 29 Fission chamber was covered with Cd tube closed at one 23370 1 30 end 1.58 inch long, 1/4 inch internal diameter, 0.040 23370 1 31 inch wall (0.533 eV Cd cut-off). 23370 1 32 HISTORY (20180725C) M.M. 23370 1 33 ENDBIB 31 0 23370 1 34 NOCOMMON 0 0 23370 1 35 ENDSUBENT 34 0 23370 199999 SUBENT 23370002 20180725 226923370 2 1 BIB 3 8 23370 2 2 REACTION (92-U-233(N,F),,RI) 23370 2 3 METHOD Measuring position U-233/boron 23370 2 4 Mean moderator 3.225 23370 2 5 Center uranium in graphite lattice 3.229 23370 2 6 Mean for moderator and uranium position 3.227 23370 2 7 U-233/boron was derived from U-235/boron and U-233/U2323370 2 8 integral ratios. 23370 2 9 STATUS (TABLE) Table 8 of Conf.Proc. 58GENEVA,16,233,1958 23370 2 10 ENDBIB 8 0 23370 2 11 NOCOMMON 0 0 23370 2 12 DATA 2 2 23370 2 13 EN-MIN DATA 23370 2 14 EV B 23370 2 15 0.533 757. 23370 2 16 0.67 961. 23370 2 17 ENDDATA 4 0 23370 2 18 ENDSUBENT 17 0 23370 299999 SUBENT 23370003 20180725 226923370 3 1 BIB 5 17 23370 3 2 REACTION (92-U-235(N,F),,RI) 23370 3 3 DETECTOR (IOCH) Boron ionization chamber of the same geometry 23370 3 4 was used to compare the Cd ratios of B and U-235 in the23370 3 5 same spectrum. 23370 3 6 MONITOR Boron epicadmium integral. 23370 3 7 METHOD Calibration measurement for U-235. 23370 3 8 Measuring position Boron U-235 U-235/boron 23370 3 9 Cd ratio Cd ratio 23370 3 10 Moderator position 23370 3 11 in graphite lattice 23.75 21.23 1.053 23370 3 12 GLEEP oscillator 35.0 30.6 1.076 23370 3 13 Mean moderator 1.065 23370 3 14 Center uranium 23370 3 15 in graphite lattice 13.51 12.42 1.018 23370 3 16 Mean for moderator and 23370 3 17 uranium position 1.041 23370 3 18 STATUS (TABLE) Table 8 of Conf.Proc. 58GENEVA,16,233,1958 23370 3 19 ENDBIB 17 0 23370 3 20 NOCOMMON 0 0 23370 3 21 DATA 2 2 23370 3 22 EN-MIN DATA 23370 3 23 EV B 23370 3 24 0.533 268. 23370 3 25 0.67 239. 23370 3 26 ENDDATA 4 0 23370 3 27 ENDSUBENT 26 0 23370 399999 SUBENT 23370004 20180725 226923370 4 1 BIB 3 8 23370 4 2 REACTION (94-PU-239(N,F),,RI) 23370 4 3 METHOD Measuring position Pu-239/boron 23370 4 4 Mean moderator 0.969 23370 4 5 Center uranium in graphite lattice 1.013 23370 4 6 Mean for moderator and uranium position 0.991 23370 4 7 U-233/boron was derived from Pu-239/boron and 23370 4 8 Pu-239/U235 integral ratios. 23370 4 9 STATUS (TABLE) Table 8 of Conf.Proc. 58GENEVA,16,233,1958 23370 4 10 ENDBIB 8 0 23370 4 11 NOCOMMON 0 0 23370 4 12 DATA 2 2 23370 4 13 EN-MIN DATA 23370 4 14 EV B 23370 4 15 0.533 316. 23370 4 16 0.67 282. 23370 4 17 ENDDATA 4 0 23370 4 18 ENDSUBENT 17 0 23370 499999 SUBENT 23370005 20180725 226923370 5 1 BIB 4 9 23370 5 2 REACTION ((92-U-233(N,F),,RI)/(92-U-235(N,F),,RI)) 23370 5 3 ANALYSIS Mean value for systems investigated (see Table 4) 23370 5 4 FLAG (1.) 1-7 refs. for systems 23370 5 5 (2.) 8-12 refs. for systems 23370 5 6 (3.) 13-35 refs. for systems 23370 5 7 (4.) 36-48 refs. for systems 23370 5 8 (5.) 49-50 for all moderators positions 23370 5 9 (6.) 51-52 for all uranium position 23370 5 10 STATUS (TABLE) Table 5 of Conf.Proc. 58GENEVA,16,233,1958 23370 5 11 ENDBIB 9 0 23370 5 12 COMMON 1 3 23370 5 13 EN-MIN 23370 5 14 EV 23370 5 15 0.533 23370 5 16 ENDCOMMON 3 0 23370 5 17 DATA 3 6 23370 5 18 DATA DATA-ERR FLAG 23370 5 19 NO-DIM NO-DIM NO-DIM 23370 5 20 2.957 0.103 1. 23370 5 21 3.21 0.18 2. 23370 5 22 3.051 0.022 3. 23370 5 23 3.166 0.027 4. 23370 5 24 3.028 0.021 5. 23370 5 25 3.172 0.059 6. 23370 5 26 ENDDATA 8 0 23370 5 27 ENDSUBENT 26 0 23370 599999 SUBENT 23370006 20180725 226923370 6 1 BIB 4 9 23370 6 2 REACTION ((94-PU-239(N,F),,RI)/(92-U-235(N,F),,RI)) 23370 6 3 ANALYSIS Mean value for systems investigated (see Table 4) 23370 6 4 FLAG (1.) 1-7 refs. for systems 23370 6 5 (2.) 8-12 refs. for systems 23370 6 6 (3.) 13-35 refs. for systems 23370 6 7 (4.) 36-48 refs. for systems 23370 6 8 (5.) 49-50 for all moderators positions 23370 6 9 (6.) 51-52 for all uranium position 23370 6 10 STATUS (TABLE) Table 5 of Conf.Proc. 58GENEVA,16,233,1958 23370 6 11 ENDBIB 9 0 23370 6 12 COMMON 1 3 23370 6 13 EN-MIN 23370 6 14 EV 23370 6 15 0.533 23370 6 16 ENDCOMMON 3 0 23370 6 17 DATA 3 6 23370 6 18 DATA DATA-ERR FLAG 23370 6 19 NO-DIM NO-DIM NO-DIM 23370 6 20 0.871 0.047 1. 23370 6 21 1.008 0.024 2. 23370 6 22 0.921 0.007 3. 23370 6 23 0.991 0.010 4. 23370 6 24 0.910 0.015 5. 23370 6 25 0.995 0.012 6. 23370 6 26 ENDDATA 8 0 23370 6 27 ENDSUBENT 26 0 23370 699999 ENDENTRY 6 0 2337099999999