ENTRY 23592 20210308 22992359200000001 SUBENT 23592001 20210308 22992359200100001 BIB 14 43 2359200100002 TITLE Delayed neutron yields from 14.8 MeV neutron induced 2359200100003 fission of 238U, 232Th and 231Pa 2359200100004 AUTHOR (M.G.Brown,S.J.Lyle,E.B.M.Martin) 2359200100005 REFERENCE (J,RCA,15,109,1971) 2359200100006 INSTITUTE (2UK KEN) 2359200100007 FACILITY (NGEN,2UK KEN) SAMES neutron generator 2359200100008 INC-SOURCE (D-T) 2359200100009 SAMPLE Pa-231 of 7.25 g as Pa(2)O(5). 2359200100010 Th-232 as metal powder (8 to 10 g). 2359200100011 U-238 as UO(3) depleted in U-235 ( 8 to 10 g). 2359200100012 Packed in separate capsules. 2359200100013 The capsule was irradiated in a standard position 2359200100014 close to the neutron source. 2359200100015 DETECTOR (SOLST) Semi-conductor detector for counting of 2359200100016 alpha-particles from H-3(d,n)He-4 reaction to monitor 2359200100017 neutron flux. 2359200100018 (BF3) Array of 20 proportional counters filled with 2359200100019 B-10 enriched BF3 for delay neutrons counting. 2359200100020 Standard source of ~8 mg RaBeF(4) was used to check 2359200100021 efficiency of delayed neutron counting set. 2359200100022 The delayed neutron counting set was checked by 2359200100023 V-51(p,n)Cr-51 and Fe(P,n)Co-57 reactions (irradiation 2359200100024 at VDG of AERE) and standard source of Cr-51 or Co-57. 2359200100025 Detection efficiency dependence from neutron energy is 2359200100026 presented on Fig.1 of Radiochimica Acta,v.15,p.109,19712359200100027 METHOD Irradiation time 12.1 or 60 sec. 2359200100028 Pneumatic transfer system moved the capsule between 2359200100029 irradiation position and the counting position within 2359200100030 the ring of neutron counters. 2359200100031 MONITOR ((MONIT1)26-FE-56(N,P)25-MN-56,,SIG) 2359200100032 For incident neutron flux. 2359200100033 MONIT-REF ((MONIT1),J.D.Hemingway+,J,PRS/A,292,180,1966) 2359200100034 ANALYSIS Delay neutron decay curves were resolved into four 2359200100035 groups. 2359200100036 Formula (1) of Radiochimica Acta,v.15,p.109,1971 was 2359200100037 used to determine the yield of the particular group. 2359200100038 Mean counting efficiency for each group was determined 2359200100039 by neutron spectra from rel.ref. of R.Batchelor+ for 2359200100040 groups 1 -4 from U-235 thermal neutron fission: 2359200100041 Group 1 2 3 4 2359200100042 Efficiency,% 6.31 6.49 6.44 6.40 2359200100043 REL-REF (R,,R.Batchelor+,J,JNE,3,7,1956) 2359200100044 HISTORY (20210308C) M.M. 2359200100045 ENDBIB 43 0 2359200100046 COMMON 3 3 2359200100047 EN EN-ERR MONIT1 2359200100048 MEV MEV MB 2359200100049 14.8 0.2 97. 2359200100050 ENDCOMMON 3 0 2359200100051 ENDSUBENT 50 0 2359200199999 SUBENT 23592002 20210308 22992359200200001 BIB 5 7 2359200200002 REACTION (92-U-238(N,F),DL/GRP,NU) 2359200200003 MONITOR ((MONIT2)92-U-238(N,F),,SIG) 2359200200004 MONIT-REF (,D.J.Hughes+,R,BNL-325,1958) 2nd edition. 2359200200005 ERR-ANALYS (DATA-ERR) Standard errors are estimated to be about 2359200200006 15 % 2359200200007 STATUS (TABLE) Table 3 - data, Table 1 - HL 2359200200008 of Radiochimica Acta,v.15,p.109,1971. 2359200200009 ENDBIB 7 0 2359200200010 COMMON 2 3 2359200200011 DATA-ERR MONIT2 2359200200012 PER-CENT B 2359200200013 15. 1.17 2359200200014 ENDCOMMON 3 0 2359200200015 DATA 2 4 2359200200016 HL DATA 2359200200017 SEC PC/FIS 2359200200018 56.11 0.077 2359200200019 21.92 0.50 2359200200020 5.20 0.62 2359200200021 2.27 0.62 2359200200022 ENDDATA 6 0 2359200200023 ENDSUBENT 22 0 2359200299999 SUBENT 23592003 20210308 22992359200300001 BIB 5 7 2359200300002 REACTION (92-U-238(N,F),DL,NU) 2359200300003 MONITOR ((MONIT2)92-U-238(N,F),,SIG) 2359200300004 MONIT-REF (,D.J.Hughes+,R,BNL-325,1958) 2nd edition. 2359200300005 ERR-ANALYS (DATA-ERR) Standard errors are estimated to be about 2359200300006 15 % 2359200300007 STATUS (TABLE) Table 3 of Radiochimica Acta,v.15,p.109,1971. 2359200300008 (DEP,23592002) Delayed neutron groups. 2359200300009 ENDBIB 7 0 2359200300010 COMMON 2 3 2359200300011 DATA-ERR MONIT2 2359200300012 PER-CENT B 2359200300013 15. 1.17 2359200300014 ENDCOMMON 3 0 2359200300015 DATA 1 1 2359200300016 DATA 2359200300017 PC/FIS 2359200300018 1.82 2359200300019 ENDDATA 3 0 2359200300020 ENDSUBENT 19 0 2359200399999 SUBENT 23592004 20210308 22992359200400001 BIB 5 7 2359200400002 REACTION (90-TH-232(N,F),DL/GRP,NU) 2359200400003 MONITOR ((MONIT2)90-TH-232(N,F),,SIG) 2359200400004 MONIT-REF (,D.J.Hughes+,R,BNL-325,1958) 2nd edition. 2359200400005 ERR-ANALYS (DATA-ERR) Standard errors are estimated to be about 2359200400006 15 % 2359200400007 STATUS (TABLE) Table 4 - data, Table 1 - HL 2359200400008 of Radiochimica Acta,v.15,p.109,1971. 2359200400009 ENDBIB 7 0 2359200400010 COMMON 2 3 2359200400011 DATA-ERR MONIT2 2359200400012 PER-CENT B 2359200400013 15. 0.32 2359200400014 ENDCOMMON 3 0 2359200400015 DATA 2 4 2359200400016 HL DATA 2359200400017 SEC PC/FIS 2359200400018 53.80 0.23 2359200400019 19.07 0.67 2359200400020 6.42 0.74 2359200400021 2.15 1.05 2359200400022 ENDDATA 6 0 2359200400023 ENDSUBENT 22 0 2359200499999 SUBENT 23592005 20210308 22992359200500001 BIB 5 7 2359200500002 REACTION (90-TH-232(N,F),DL,NU) 2359200500003 MONITOR ((MONIT2)90-TH-232(N,F),,SIG) 2359200500004 MONIT-REF (,D.J.Hughes+,R,BNL-325,1958) 2nd edition. 2359200500005 ERR-ANALYS (DATA-ERR) Standard errors are estimated to be about 2359200500006 15 % 2359200500007 STATUS (TABLE) Table 4 of Radiochimica Acta,v.15,p.109,1971. 2359200500008 (DEP,23592004) Delayed neutron groups. 2359200500009 ENDBIB 7 0 2359200500010 COMMON 2 3 2359200500011 DATA-ERR MONIT2 2359200500012 PER-CENT B 2359200500013 15. 0.32 2359200500014 ENDCOMMON 3 0 2359200500015 DATA 1 1 2359200500016 DATA 2359200500017 PC/FIS 2359200500018 2.69 2359200500019 ENDDATA 3 0 2359200500020 ENDSUBENT 19 0 2359200599999 SUBENT 23592006 20210308 22992359200600001 BIB 7 15 2359200600002 REACTION (91-PA-231(N,F),DL/GRP,NU) 2359200600003 MONITOR ((MONIT2)91-PA-231(N,F),,SIG) 2359200600004 MONIT-REF (,O.Birgul+,J,RCA,11,108,1969) 2359200600005 MISC-COL (MISC1) Calculated following the procedure and using 2359200600006 the parameters employed by S.Amiel+, but with a 4.25 2359200600007 prompt neutron yield per fission and chain yields from 2359200600008 Brown+ 2359200600009 (MISC2) Calculated as MISC1 but using delayed neutron 2359200600010 emission probabilities from Del Marmol. 2359200600011 REL-REF (R,,S.Amiel+,C,67VIENNA,,,1967) 2359200600012 (R,,M.G.Brown+,J,RCA,6,16,1966) 2359200600013 ERR-ANALYS (DATA-ERR) Standard errors are estimated to be about 2359200600014 15 % 2359200600015 STATUS (TABLE) Table 5 - data, Table 1 - HL 2359200600016 of Radiochimica Acta,v.15,p.109,1971. 2359200600017 ENDBIB 15 0 2359200600018 COMMON 2 3 2359200600019 DATA-ERR MONIT2 2359200600020 PER-CENT B 2359200600021 25. 1.42 2359200600022 ENDCOMMON 3 0 2359200600023 DATA 4 4 2359200600024 HL DATA MISC1 MISC2 2359200600025 SEC PC/FIS PC/FIS PC/FIS 2359200600026 53.4 0.082 0.061 0.064 2359200600027 19.2 0.15 0.122 0.132 2359200600028 5.5 0.18 0.084 0.085 2359200600029 2.0 0.19 0.108 0.113 2359200600030 ENDDATA 6 0 2359200600031 ENDSUBENT 30 0 2359200699999 SUBENT 23592007 20210308 22992359200700001 BIB 6 9 2359200700002 REACTION (91-PA-231(N,F),DL,NU) 2359200700003 MONITOR ((MONIT2)91-PA-231(N,F),,SIG) 2359200700004 MONIT-REF (,O.Birgul+,J,RCA,11,108,1969) 2359200700005 MISC-COL (MISC1) Calculated by group yields of MISC1 in Sub.006 2359200700006 (MISC2) Calculated by group yields of MISC2 in Sub.006 2359200700007 ERR-ANALYS (DATA-ERR) Standard errors are estimated to be about 2359200700008 15 % 2359200700009 STATUS (TABLE) Table 5 of Radiochimica Acta,v.15,p.109,1971. 2359200700010 (DEP,23592006) Delayed neutron groups. 2359200700011 ENDBIB 9 0 2359200700012 COMMON 2 3 2359200700013 DATA-ERR MONIT2 2359200700014 PER-CENT B 2359200700015 25. 1.4 2359200700016 ENDCOMMON 3 0 2359200700017 DATA 3 1 2359200700018 DATA MISC1 MISC2 2359200700019 PC/FIS PC/FIS PC/FIS 2359200700020 0.60 0.38 0.39 2359200700021 ENDDATA 3 0 2359200700022 ENDSUBENT 21 0 2359200799999 ENDENTRY 7 0 2359299999999