ENTRY 14722 20211211 14951472200000001 SUBENT 14722001 20211211 14951472200100001 BIB 8 19 1472200100002 TITLE Capture cross sections for 240 Kev neutrons of gold, 1472200100003 rhenium and uranium 1472200100004 AUTHOR (G.A.Linenberger,M.L.Perlman,E.Segre) 1472200100005 REFERENCE (R,LA-16,1943) 1472200100006 INSTITUTE (1USALAS) 1472200100007 INC-SOURCE (PHOTO) The yttrium source was embedded in a cube of 1472200100008 beryllium having a 4 cm side. 1472200100009 DETECTOR (IOCH,GEMUC) Ionization chamber for fission, Geiger 1472200100010 counter for beta activities. 1472200100011 METHOD (EXTB) The capture cross sections were using Y+Be 1472200100012 source and detecting the beta radioactivity formed in 1472200100013 the sample irradiated. The yttrium source cube was 1472200100014 put in contact with an enriched sample of known 235U 1472200100015 content and fission produced were measured in 1472200100016 ionization chamber with a linear amplifier. In this 1472200100017 way, knowing the cross section of 235U, one can 1472200100018 calculate the neutron flux through a sample having a 1472200100019 geometry of the 235U sample. 1472200100020 HISTORY (20211211C) BP 1472200100021 ENDBIB 19 0 1472200100022 COMMON 1 3 1472200100023 EN 1472200100024 KEV 1472200100025 240.0 1472200100026 ENDCOMMON 3 0 1472200100027 ENDSUBENT 26 0 1472200199999 SUBENT 14722002 20211211 14951472200200001 BIB 4 5 1472200200002 REACTION 1((79-AU-197(N,G)79-AU-198,,SIG)/(92-U-235(N,F),,SIG)) 1472200200003 2(79-AU-197(N,G)79-AU-198,,SIG) 1472200200004 MONITOR 2(92-U-235(N,F),,SIG) 1472200200005 ERR-ANALYS (DATA-ERR) Experimental errors. 1472200200006 STATUS (TABLE) page 5. 1472200200007 ENDBIB 5 0 1472200200008 NOCOMMON 0 0 1472200200009 DATA 4 1 1472200200010 DATA 1DATA-ERR 1DATA 2MONIT 2 1472200200011 NO-DIM NO-DIM B B 1472200200012 0.28 0.06 0.7 2.5 1472200200013 ENDDATA 3 0 1472200200014 ENDSUBENT 13 0 1472200299999 SUBENT 14722003 20211211 14951472200300001 BIB 4 5 1472200300002 REACTION 1((75-RE-187(N,G)75-RE-188,,SIG)/(92-U-235(N,F),,SIG)) 1472200300003 2(75-RE-187(N,G)75-RE-188,,SIG) 1472200300004 MONITOR 2(92-U-235(N,F),,SIG) 1472200300005 ERR-ANALYS (DATA-ERR) Experimental errors. 1472200300006 STATUS (TABLE) page 5. 1472200300007 ENDBIB 5 0 1472200300008 NOCOMMON 0 0 1472200300009 DATA 4 1 1472200300010 DATA 1DATA-ERR 1DATA 2MONIT 2 1472200300011 NO-DIM NO-DIM B B 1472200300012 0.53 0.1 1.3 2.5 1472200300013 ENDDATA 3 0 1472200300014 ENDSUBENT 13 0 1472200399999 SUBENT 14722004 20211211 14951472200400001 BIB 4 5 1472200400002 REACTION 1((75-RE-185(N,G)75-RE-186,,SIG)/(92-U-235(N,F),,SIG)) 1472200400003 2(75-RE-185(N,G)75-RE-186,,SIG) 1472200400004 MONITOR 2(92-U-235(N,F),,SIG) 1472200400005 ERR-ANALYS (DATA-ERR) Experimental errors. 1472200400006 STATUS (TABLE) page 5. 1472200400007 ENDBIB 5 0 1472200400008 NOCOMMON 0 0 1472200400009 DATA 4 1 1472200400010 DATA 1DATA-ERR 1DATA 2MONIT 2 1472200400011 NO-DIM NO-DIM B B 1472200400012 0.47 0.1 1.2 2.5 1472200400013 ENDDATA 3 0 1472200400014 ENDSUBENT 13 0 1472200499999 SUBENT 14722005 20211211 14951472200500001 BIB 6 10 1472200500002 REACTION 1((92-U-238(N,G)92-U-239,,SIG)/(92-U-235(N,F),,SIG)) 1472200500003 2(92-U-238(N,G)92-U-239,,SIG) 1472200500004 MONITOR 2(92-U-235(N,F),,SIG) 1472200500005 SAMPLE 60 grams of U3O8. 1472200500006 METHOD (CHSEP) The irradiated oxide was dissolved with 1472200500007 nitric acid; Sulphur dioxide was added to insure the 1472200500008 93 being in the oxidation state. This sample was used 1472200500009 in measurements. 1472200500010 ERR-ANALYS (DATA-ERR) Experimental errors. 1472200500011 STATUS (TABLE) page 8. 1472200500012 ENDBIB 10 0 1472200500013 NOCOMMON 0 0 1472200500014 DATA 4 1 1472200500015 DATA 1DATA-ERR 1DATA 2MONIT 2 1472200500016 NO-DIM NO-DIM B B 1472200500017 0.066 0.001 0.165 2.5 1472200500018 ENDDATA 3 0 1472200500019 ENDSUBENT 18 0 1472200599999 ENDENTRY 5 0 1472299999999