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