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