ENTRY 23350 20201211 22962335000000001 SUBENT 23350001 20201211 22962335000100001 BIB 11 21 2335000100002 TITLE Delayed neutron precursors-III Selenium-87 2335000100003 AUTHOR (L.Tomlinson, M.H.Hurdus) 2335000100004 REFERENCE (J,JIN,30,1995,1968) 2335000100005 INSTITUTE (2UK HAR) AERE,Harwell,Didcot,Berkshire 2335000100006 REL-REF (M,23351001,L.Tomlinson+,J,JIN,30,1125,1968) 2335000100007 Method of irradiation. 2335000100008 FACILITY (REAC,2UK HAR) 2335000100009 INC-SOURCE (REAC) 2335000100010 METHOD (CHSEP) Separation of Se fission product base of the 2335000100011 formation of H(2)Se. 2335000100012 Delay experiments: 2335000100013 Delay before Se separation, sec 0 5.0 10. 18.1 2335000100014 Residual neutron flux,% of max. 8 0.2 0.0002 0.003 2335000100015 Se chemical yield, 0.73 0.35 0.52 0.56 2335000100016 HL,sec 54.2 49.9 52.0 60.5 2335000100017 +- standard deviation, sec 1.2 4.5 2.0 3.8 2335000100018 DETECTOR No information about neutron detector in 2335000100019 J.Inorg.Nucl.Chem.,30,1995,1968 2335000100020 ANALYSIS (DECAY) Neutron decay curve analyzed. 2335000100021 HISTORY (20171031C) M.M. 2335000100022 (20201211U) SD: Correction in Subent 002. 2335000100023 ENDBIB 21 0 2335000100024 NOCOMMON 0 0 2335000100025 ENDSUBENT 24 0 2335000199999 SUBENT 23350002 20201211 22962335000200001 BIB 8 17 2335000200002 REACTION (92-U-235(N,F)34-SE-87,CUM,FY,,SPA) 2335000200003 DECAY-DATA (34-SE-87,5.8SEC) 5.8+-0.5 sec measured HL 2335000200004 (35-BR-87,55.SEC,DN,,0.028) 2335000200005 Weighted mean of two exp.values of Herrmann 2335000200006 RAD-DET (35-BR-87,DN) 2335000200007 REL-REF (R,22571001,G.Herrmann,C,67VIENNA,,147,1967) 2335000200008 Neutron branching ratio for Br-87 - 2.8+-0.4% . 2335000200009 (A,,L.E.Weaver+,R,USNRDL-TR-633,1963) 2335000200010 Theoretical cumulative yield 1.09% . 2335000200011 ANALYSIS The cumulative fission yield of Se-87 was calculated 2335000200012 from the measured neutron activity of Br-87, grown 2335000200013 in from Se-87. 2335000200014 ERR-ANALYS (DATA-ERR) Standard deviation 2335000200015 Mid-separation time error +-0.5sec. 2335000200016 STATUS (TABLE) Text, p.2000 of J.Inorg.Nucl.Chem.,30,1995,19682335000200017 HISTORY (20201211U) SD: DECAY-DATA corrected (missed comma 2335000200018 before intensity added). 2335000200019 ENDBIB 17 0 2335000200020 COMMON 1 3 2335000200021 EN-DUMMY 2335000200022 EV 2335000200023 0.0253 2335000200024 ENDCOMMON 3 0 2335000200025 DATA 2 1 2335000200026 DATA DATA-ERR 2335000200027 PC/FIS PC/FIS 2335000200028 1.17 0.24 2335000200029 ENDDATA 3 0 2335000200030 ENDSUBENT 29 0 2335000299999 SUBENT 23350003 20171031 22682335000300001 BIB 5 11 2335000300002 REACTION (34-SE-87(0,B-)35-BR-87,,PN) 2335000300003 DECAY-DATA (34-SE-87,5.8SEC) 5.8+-0.5 sec measured HL 2335000300004 ANALYSIS -Pn was calculated using half-life and fission yield, 2335000300005 assuming that all of short-lived activity is due to 2335000300006 Se-87 to be < 1.5 %. 2335000300007 -Pn was calculated from the shape of the neutron decay 2335000300008 curve using half-lives for Se-87 and Br-87 and Pn for 2335000300009 Br-87 and measured neutron activities . This value is 2335000300010 more accurate. 2335000300011 ASSUMED (ASSUM,35-BR-87(0,B-)36-KR-87,,PN) 2.8 % 2335000300012 STATUS (TABLE) Text, p.2002 of J.Inorg.Nucl.Chem.,30,1995,19682335000300013 ENDBIB 11 0 2335000300014 NOCOMMON 0 0 2335000300015 DATA 2 1 2335000300016 DATA-MAX ASSUM 2335000300017 NO-DIM NO-DIM 2335000300018 0.008 0.028 2335000300019 ENDDATA 3 0 2335000300020 ENDSUBENT 19 0 2335000399999 SUBENT 23350004 20171031 22682335000400001 BIB 4 8 2335000400002 REACTION (92-U-235(N,F)34-SE-87,DL/CUM,NU,,SPA) 2335000400003 Absolute delayed neutron yield from Se-87 2335000400004 DECAY-DATA (34-SE-87,5.8SEC) 5.8+-0.5 sec measured HL 2335000400005 ANALYSIS Calculated as measured Se-87 cumulative yield 2335000400006 multiplied by measured Pn value. 2335000400007 STATUS (TABLE) Text, p.2002 of J.Inorg.Nucl.Chem.,30,1995,19682335000400008 (DEP,23350003) Pn value. 2335000400009 (DEP,23350002) Se-87 cumulative fission yield 2335000400010 ENDBIB 8 0 2335000400011 COMMON 1 3 2335000400012 EN-DUMMY 2335000400013 EV 2335000400014 0.0253 2335000400015 ENDCOMMON 3 0 2335000400016 DATA 1 1 2335000400017 DATA-MAX 2335000400018 PC/FIS 2335000400019 1.0E-2 2335000400020 ENDDATA 3 0 2335000400021 ENDSUBENT 20 0 2335000499999 ENDENTRY 4 0 2335099999999