ENTRY            40955   20180202                             41784095500000001 
SUBENT        40955001   20180202                             41784095500100001 
BIB                 12         38                                 4095500100002 
TITLE       Measurement of the resonance integral and evaluation  4095500100003 
            of the absorption cross-section for thermal neutrons  4095500100004 
            for the radioactive Cd-109                            4095500100005 
AUTHOR     (M.P.Anikina,A.G.Beda,A.V.Davydov,M.M.Korotkov,        4095500100006 
           G.M.Kukavadze,L.Ya.Memelova)                           4095500100007 
INSTITUTE  (4RUSITE)                                              4095500100008 
REFERENCE  (J,AE,62,415,1987) Issue 6.                            4095500100009 
           (J,SJA,62,483,1987) Engl.transl.of J,AE,62,415,1987    4095500100010 
FACILITY   (REAC,4RUSITE) Heavy-water reactor                     4095500100011 
INC-SOURCE (REAC)                                                 4095500100012 
SAMPLE      Cd-109 obtained after silver irradiation in           4095500100013 
            a cyclotron                                           4095500100014 
DETECTOR   (GELI)                                                 4095500100015 
ERR-ANALYS (DATA-ERR)  Not specified                              4095500100016 
METHOD     (ACTIV)  Irradiation with and without Cd.              4095500100017 
            Irradiation time 306.44 hr.                           4095500100018 
            Gamma-activity of samples:                            4095500100019 
           Sample number 1 :                                      4095500100020 
           Irradiation           in Cd 1mm thick                  4095500100021 
           Activity ratio A1/A3                                   4095500100022 
           before irradiation    0.84083+-0.00085                 4095500100023 
           after irradiation     0.83273+-0.00117                 4095500100024 
           Sample number 2 :                                      4095500100025 
           Irradiation           without Cd                       4095500100026 
           Activity ratio A2/A3                                   4095500100027 
           before irradiation    1.26833+-0.00145                 4095500100028 
           after irradiation     1.25286+-0.00207                 4095500100029 
DECAY-DATA (48-CD-109,,DG,88.)                                    4095500100030 
HISTORY    (19880701C)  Compiled at the CJD                       4095500100031 
           (19920727U) Reference Code Corrected, 'ASSUMED' in     4095500100032 
                     'MONITOR' converted, EN-NRM and EN-NRM-MIN   4095500100033 
                     deleted                                      4095500100034 
           (20180202A) M.M. Upper -> lower case correction.       4095500100035 
           Dates were corrected for 4-digits year.                4095500100036 
           Ref. SJA,62,483,1987 was added.                        4095500100037 
           MONITOR -> ASSUM ( not directly proportional values,   4095500100038 
           see formula1 9,10 in SJA,62,483,1987 ) and moved in    4095500100039 
           data Subents.                                          4095500100040 
ENDBIB              38          0                                 4095500100041 
NOCOMMON             0          0                                 4095500100042 
ENDSUBENT           41          0                                 4095500199999 
SUBENT        40955002   20180202                             41784095500200001 
BIB                  4          7                                 4095500200002 
REACTION   (48-CD-109(N,ABS),,SIG,,SPA)  Averaged over reactor    4095500200003 
                                         thermal spectrum         4095500200004 
INC-SPECT   Reactor thermal neutron spectrum.                     4095500200005 
           Thermal flux was determined by Co monitor :            4095500200006 
            (1.342+-0.052)*10**13                                 4095500200007 
ASSUMED    (ASSUM1,48-CD-108(N,ABS),,SIG)                         4095500200008 
STATUS     (TABLE) Text page 484 of SJA,62,483,1987               4095500200009 
ENDBIB               7          0                                 4095500200010 
COMMON               2          3                                 4095500200011 
ASSUM1     ASSUM1-ERR                                             4095500200012 
B          B                                                      4095500200013 
 1.1         .3                                                   4095500200014 
ENDCOMMON            3          0                                 4095500200015 
DATA                 3          1                                 4095500200016 
EN-DUMMY   DATA       DATA-ERR                                    4095500200017 
EV         B          B                                           4095500200018 
 0.0253     184.       180.                                       4095500200019 
ENDDATA              3          0                                 4095500200020 
ENDSUBENT           19          0                                 4095500299999 
SUBENT        40955003   20180202                             41784095500300001 
BIB                  4          5                                 4095500300002 
REACTION   (48-CD-109(N,ABS),,RI)                                 4095500300003 
INC-SPECT  Epithermal flux was determined by Co monitor :         4095500300004 
             (1.332+-0.060)*10**12 n/cm2/sec                      4095500300005 
ASSUMED    (ASSUM2,48-CD-108(N,ABS),,RI)                          4095500300006 
STATUS     (TABLE) Text page 484 of SJA,62,483,1987               4095500300007 
ENDBIB               5          0                                 4095500300008 
COMMON               2          3                                 4095500300009 
ASSUM2     ASSUM2-ERR                                             4095500300010 
B          B                                                      4095500300011 
 12.8       1.8                                                   4095500300012 
ENDCOMMON            3          0                                 4095500300013 
DATA                 3          1                                 4095500300014 
EN-MIN     DATA       DATA-ERR                                    4095500300015 
EV         B          B                                           4095500300016 
  0.5        6.720E+03    1.2E+03                                 4095500300017 
ENDDATA              3          0                                 4095500300018 
ENDSUBENT           17          0                                 4095500399999 
ENDENTRY             3          0                                 4095599999999