ENTRY 12661 20080724 13481266100000001 SUBENT 12661001 20080724 13481266100100001 BIB 11 23 1266100100002 INSTITUTE (1USAMIS) 1266100100003 REFERENCE (J,NIM,145,245,1977) 1266100100004 AUTHOR (R.B.Royer,R.M.Brugger) 1266100100005 TITLE Development of a 238U filtered beam of 186 eV neutrons 1266100100006 FACILITY (REAC,1USAMIS) Missouri University Reasearch Reactor. 1266100100007 INC-SOURCE (REAC) 238U filtered beam. 1266100100008 METHOD Beam filtered through natural uranium slug encapsulated1266100100009 in Al and pressed in Fe sleeves. Runs taken with U 1266100100010 bearing Fe sleeves and Fe sleeves alone. 1266100100011 Se, Mn and Ge were added to uranium to reduce 1266100100012 the background of other energy neutrons. 1266100100013 Beam purity (percentage of beam intensity due to 186 1266100100014 eV neutrons as compared to total beam intensity) 1266100100015 measured as a function of thickness of filter 1266100100016 components using W sample and W in - W out technique. 1266100100017 DETECTOR (PROPC) 10BF3 gas filled proportional counter. 1266100100018 MONITOR Absolute flux calibrated at 24 keV using Fe filter. 1266100100019 ERR-ANALYS (ERR-S) Standard deviation from the calculation of 1266100100020 transmission. 1266100100021 HISTORY (19840410C) 1266100100022 (19860114A) Author corrected. 1266100100023 (20080724A) Converted to new date formats, lower case. 1266100100024 Energy corrected, BIB updates. 1266100100025 ENDBIB 23 0 1266100100026 COMMON 1 3 1266100100027 EN 1266100100028 EV 1266100100029 186. 1266100100030 ENDCOMMON 3 0 1266100100031 ENDSUBENT 30 0 1266100199999 SUBENT 12661002 20080724 13481266100200001 BIB 2 2 1266100200002 REACTION (5-B-10(N,TOT),,SIG) 1266100200003 SAMPLE 90%-enriched 10B powder sample. 1266100200004 ENDBIB 2 0 1266100200005 NOCOMMON 0 0 1266100200006 DATA 2 1 1266100200007 DATA ERR-S 1266100200008 B B 1266100200009 40.3 0.30 1266100200010 ENDDATA 3 0 1266100200011 ENDSUBENT 10 0 1266100299999 SUBENT 12661003 20080724 13481266100300001 BIB 2 2 1266100300002 REACTION (6-C-0(N,TOT),,SIG) 1266100300003 SAMPLE Natural carbon sample. 1266100300004 ENDBIB 2 0 1266100300005 NOCOMMON 0 0 1266100300006 DATA 2 1 1266100300007 DATA ERR-S 1266100300008 B B 1266100300009 4.84 0.07 1266100300010 ENDDATA 3 0 1266100300011 ENDSUBENT 10 0 1266100399999 SUBENT 12661004 20080724 13481266100400001 BIB 2 2 1266100400002 REACTION (13-AL-27(N,TOT),,SIG) 1266100400003 SAMPLE Natural aluminum sample. 1266100400004 ENDBIB 2 0 1266100400005 NOCOMMON 0 0 1266100400006 DATA 2 1 1266100400007 DATA ERR-S 1266100400008 B B 1266100400009 1.37 0.02 1266100400010 ENDDATA 3 0 1266100400011 ENDSUBENT 10 0 1266100499999 SUBENT 12661005 20080724 13481266100500001 BIB 2 2 1266100500002 REACTION (26-FE-0(N,TOT),,SIG) 1266100500003 SAMPLE Natural iron sample. 1266100500004 ENDBIB 2 0 1266100500005 NOCOMMON 0 0 1266100500006 DATA 2 1 1266100500007 DATA ERR-S 1266100500008 B B 1266100500009 12.50 0.09 1266100500010 ENDDATA 3 0 1266100500011 ENDSUBENT 10 0 1266100599999 SUBENT 12661006 20080724 13481266100600001 BIB 2 2 1266100600002 REACTION (82-PB-0(N,TOT),,SIG) 1266100600003 SAMPLE Natural lead sample. 1266100600004 ENDBIB 2 0 1266100600005 NOCOMMON 0 0 1266100600006 DATA 2 1 1266100600007 DATA ERR-S 1266100600008 B B 1266100600009 10.74 0.09 1266100600010 ENDDATA 3 0 1266100600011 ENDSUBENT 10 0 1266100699999 SUBENT 12661007 20080724 13481266100700001 BIB 2 2 1266100700002 REACTION (92-U-238(N,TOT),,SIG) 1266100700003 SAMPLE Depleted uranium sample - 0.22% 238U. 1266100700004 ENDBIB 2 0 1266100700005 NOCOMMON 0 0 1266100700006 DATA 2 1 1266100700007 DATA ERR-S 1266100700008 B B 1266100700009 1.37 0.10 1266100700010 ENDDATA 3 0 1266100700011 ENDSUBENT 10 0 1266100799999 ENDENTRY 7 0 1266199999999