ENTRY 23370 20180726 22692337000000001 SUBENT 23370001 20180726 22692337000100001 BIB 10 31 2337000100002 AUTHOR (C.G.Campbell,R.G.Freemantle, M.J.Poole) 2337000100003 TITLE Measurements of reactor spectra by time-of-flight and 2337000100004 integral methods 2337000100005 REFERENCE (C,58GENEVA,16,233,1958) 2337000100006 INSTITUTE (2UK HAR) 2337000100007 REL-REF (M,,M.J.Poole,J,JNE,5,325,1957) 2337000100008 Pulse source method details and some results. 2337000100009 (R,,C.G.Campbell+,R,AERE-RP/R-2031,1957) 2337000100010 Thermal fission rate data, used for normalization. 2337000100011 FACILITY (REAC,2UK HAR) BEPO reactor and NERO reactor, 2337000100012 DIDO mockup in DIMPLE 2337000100013 (OSCIP,2UK HAR) GLEEP oscillator 2337000100014 (CRASS,2UK HAR) Sub-critical assemblies for spectrum 2337000100015 work 2337000100016 INC-SOURCE Light water moderated lattices. 2337000100017 Graphite moderated lattices. 2337000100018 Heavy water moderated lattices. 2337000100019 Pure moderators 2337000100020 METHOD (TOF) Pulsed source method: 2337000100021 neutron spectrum was measured by TOF (12 m flight path)2337000100022 Integral method: 2337000100023 spectrum is assumed as sum of two components- 2337000100024 Maxwellian distribution with temperature T and 2337000100025 slowing down distribution with ratio epithermal to 2337000100026 thermal neutron density. 2337000100027 DETECTOR (FISCH) 1/4 inch diameter, 2 or 11 ft length. 2337000100028 Containing U-233, U-235, Pu-239 . 2337000100029 Fission chamber was covered with Cd tube closed at one 2337000100030 end 1.58 inch long, 1/4 inch internal diameter, 0.040 2337000100031 inch wall (0.533 eV Cd cut-off). 2337000100032 HISTORY (20180725C) M.M. 2337000100033 ENDBIB 31 0 2337000100034 NOCOMMON 0 0 2337000100035 ENDSUBENT 34 0 2337000199999 SUBENT 23370002 20180725 22692337000200001 BIB 3 8 2337000200002 REACTION (92-U-233(N,F),,RI) 2337000200003 METHOD Measuring position U-233/boron 2337000200004 Mean moderator 3.225 2337000200005 Center uranium in graphite lattice 3.229 2337000200006 Mean for moderator and uranium position 3.227 2337000200007 U-233/boron was derived from U-235/boron and U-233/U232337000200008 integral ratios. 2337000200009 STATUS (TABLE) Table 8 of Conf.Proc. 58GENEVA,16,233,1958 2337000200010 ENDBIB 8 0 2337000200011 NOCOMMON 0 0 2337000200012 DATA 2 2 2337000200013 EN-MIN DATA 2337000200014 EV B 2337000200015 0.533 757. 2337000200016 0.67 961. 2337000200017 ENDDATA 4 0 2337000200018 ENDSUBENT 17 0 2337000299999 SUBENT 23370003 20180725 22692337000300001 BIB 5 17 2337000300002 REACTION (92-U-235(N,F),,RI) 2337000300003 DETECTOR (IOCH) Boron ionization chamber of the same geometry 2337000300004 was used to compare the Cd ratios of B and U-235 in the2337000300005 same spectrum. 2337000300006 MONITOR Boron epicadmium integral. 2337000300007 METHOD Calibration measurement for U-235. 2337000300008 Measuring position Boron U-235 U-235/boron 2337000300009 Cd ratio Cd ratio 2337000300010 Moderator position 2337000300011 in graphite lattice 23.75 21.23 1.053 2337000300012 GLEEP oscillator 35.0 30.6 1.076 2337000300013 Mean moderator 1.065 2337000300014 Center uranium 2337000300015 in graphite lattice 13.51 12.42 1.018 2337000300016 Mean for moderator and 2337000300017 uranium position 1.041 2337000300018 STATUS (TABLE) Table 8 of Conf.Proc. 58GENEVA,16,233,1958 2337000300019 ENDBIB 17 0 2337000300020 NOCOMMON 0 0 2337000300021 DATA 2 2 2337000300022 EN-MIN DATA 2337000300023 EV B 2337000300024 0.533 268. 2337000300025 0.67 239. 2337000300026 ENDDATA 4 0 2337000300027 ENDSUBENT 26 0 2337000399999 SUBENT 23370004 20180725 22692337000400001 BIB 3 8 2337000400002 REACTION (94-PU-239(N,F),,RI) 2337000400003 METHOD Measuring position Pu-239/boron 2337000400004 Mean moderator 0.969 2337000400005 Center uranium in graphite lattice 1.013 2337000400006 Mean for moderator and uranium position 0.991 2337000400007 U-233/boron was derived from Pu-239/boron and 2337000400008 Pu-239/U235 integral ratios. 2337000400009 STATUS (TABLE) Table 8 of Conf.Proc. 58GENEVA,16,233,1958 2337000400010 ENDBIB 8 0 2337000400011 NOCOMMON 0 0 2337000400012 DATA 2 2 2337000400013 EN-MIN DATA 2337000400014 EV B 2337000400015 0.533 316. 2337000400016 0.67 282. 2337000400017 ENDDATA 4 0 2337000400018 ENDSUBENT 17 0 2337000499999 SUBENT 23370005 20180725 22692337000500001 BIB 4 9 2337000500002 REACTION ((92-U-233(N,F),,RI)/(92-U-235(N,F),,RI)) 2337000500003 ANALYSIS Mean value for systems investigated (see Table 4) 2337000500004 FLAG (1.) 1-7 refs. for systems 2337000500005 (2.) 8-12 refs. for systems 2337000500006 (3.) 13-35 refs. for systems 2337000500007 (4.) 36-48 refs. for systems 2337000500008 (5.) 49-50 for all moderators positions 2337000500009 (6.) 51-52 for all uranium position 2337000500010 STATUS (TABLE) Table 5 of Conf.Proc. 58GENEVA,16,233,1958 2337000500011 ENDBIB 9 0 2337000500012 COMMON 1 3 2337000500013 EN-MIN 2337000500014 EV 2337000500015 0.533 2337000500016 ENDCOMMON 3 0 2337000500017 DATA 3 6 2337000500018 DATA DATA-ERR FLAG 2337000500019 NO-DIM NO-DIM NO-DIM 2337000500020 2.957 0.103 1. 2337000500021 3.21 0.18 2. 2337000500022 3.051 0.022 3. 2337000500023 3.166 0.027 4. 2337000500024 3.028 0.021 5. 2337000500025 3.172 0.059 6. 2337000500026 ENDDATA 8 0 2337000500027 ENDSUBENT 26 0 2337000599999 SUBENT 23370006 20180725 22692337000600001 BIB 4 9 2337000600002 REACTION ((94-PU-239(N,F),,RI)/(92-U-235(N,F),,RI)) 2337000600003 ANALYSIS Mean value for systems investigated (see Table 4) 2337000600004 FLAG (1.) 1-7 refs. for systems 2337000600005 (2.) 8-12 refs. for systems 2337000600006 (3.) 13-35 refs. for systems 2337000600007 (4.) 36-48 refs. for systems 2337000600008 (5.) 49-50 for all moderators positions 2337000600009 (6.) 51-52 for all uranium position 2337000600010 STATUS (TABLE) Table 5 of Conf.Proc. 58GENEVA,16,233,1958 2337000600011 ENDBIB 9 0 2337000600012 COMMON 1 3 2337000600013 EN-MIN 2337000600014 EV 2337000600015 0.533 2337000600016 ENDCOMMON 3 0 2337000600017 DATA 3 6 2337000600018 DATA DATA-ERR FLAG 2337000600019 NO-DIM NO-DIM NO-DIM 2337000600020 0.871 0.047 1. 2337000600021 1.008 0.024 2. 2337000600022 0.921 0.007 3. 2337000600023 0.991 0.010 4. 2337000600024 0.910 0.015 5. 2337000600025 0.995 0.012 6. 2337000600026 ENDDATA 8 0 2337000600027 ENDSUBENT 26 0 2337000699999 ENDENTRY 6 0 2337099999999