ENTRY            30111   20240215                             32133011100000001 
SUBENT        30111001   20240215                             32133011100100001 
BIB                 15         26                                 3011100100002 
TITLE      Investigation of delayed neutrons arising from the     3011100100003 
            fission of U238 nuclei by 14.7-MeV neutrons           3011100100004 
AUTHOR     (M.Buczko)                                             3011100100005 
INSTITUTE  (3HUNDEB)                                              3011100100006 
REFERENCE  (J,SJA,20,187,1966)                                    3011100100007 
           (J,AE,20,153,1966)     Russ. orig. of SJA 20           3011100100008 
           (J,JNE,21,302,1967)    English translation of AE 20    3011100100009 
           (J,EAF,20,(2),81,1966) French translation of AE 20     3011100100010 
FACILITY   (NGEN,3HUNDEB) Atomki 300-keV neutron generator        3011100100011 
INC-SOURCE (D-D,D-T)                                              3011100100012 
SAMPLE     Natural U3O8 on polyethylene holder                    3011100100013 
METHOD     (ACTIV) Measurements began 0.5 sec after a 30 min      3011100100014 
            irradiation                                           3011100100015 
DETECTOR   (BF3) for neutron flux determination                   3011100100016 
PART-DET   (DN)                                                   3011100100017 
ANALYSIS   (DECAY) Delayed neutron decay curve obtained analysed  3011100100018 
            by graphical iteration method                         3011100100019 
CORRECTION No correction given                                    3011100100020 
ERR-ANALYS No error analysis given                                3011100100021 
STATUS     (TABLE,,M.Butsko,J,JNE,21,302,1967) Table 1            3011100100022 
           (APRVD) Approved by Angeli (6/7/72)                    3011100100023 
HISTORY    (19670830C) Compiled in DASTAR-218                     3011100100024 
           (19720106T) CA. Converted to EXFOR.                    3011100100025 
           (20050624A) OS. Reaction code in subentry 2            3011100100026 
            corrected.                                            3011100100027 
           (20240215U) On. TITLE updated.                         3011100100028 
ENDBIB              26          0                                 3011100100029 
NOCOMMON             0          0                                 3011100100030 
ENDSUBENT           29          0                                 3011100199999 
SUBENT        30111002   20050624                             31173011100200001 
BIB                  1          4                                 3011100200002 
REACTION   ((92-U-238(N,F),DL/GRP,NU)//                           3011100200003 
           (92-U-238(N,F),DL/GRP,NU))                             3011100200004 
           The yields of delayed neutrons emitted in the U-238    3011100200005 
           fission are normalised to the second group of neutrons 3011100200006 
ENDBIB               4          0                                 3011100200007 
COMMON               2          3                                 3011100200008 
EN         HL-DN                                                  3011100200009 
MEV        SEC                                                    3011100200010 
 1.4700E+01  2.000E+01                                            3011100200011 
ENDCOMMON            3          0                                 3011100200012 
DATA                 2          4                                 3011100200013 
HL-NM      DATA                                                   3011100200014 
SEC        NO-DIM                                                 3011100200015 
 5.6000E+01 1.4500E-01                                            3011100200016 
 4.6000E+00 1.0870E+00                                            3011100200017 
 1.8000E+00 2.4170E+00                                            3011100200018 
 6.0000E-01 1.4500E+00                                            3011100200019 
ENDDATA              6          0                                 3011100200020 
ENDSUBENT           19          0                                 3011100299999 
SUBENT        30111003   20050624                             31173011100300001 
BIB                  1          3                                 3011100300002 
REACTION   ((92-U-238(N,F),DL,NU)//(92-U-238(N,F),DL,NU))         3011100300003 
            Ratio of the total yield of delayed neutrons at 14.7  3011100300004 
           MeV by the total yield of delayed neutrons at 3 MeV    3011100300005 
ENDBIB               3          0                                 3011100300006 
COMMON               2          3                                 3011100300007 
EN-NM      EN-DN                                                  3011100300008 
MEV        MEV                                                    3011100300009 
 1.4700E+01 3.0000E+00                                            3011100300010 
ENDCOMMON            3          0                                 3011100300011 
DATA                 2          1                                 3011100300012 
DATA       DATA-ERR                                               3011100300013 
NO-DIM     PER-CENT                                               3011100300014 
 1.6000E+00 1.0000E+01                                            3011100300015 
ENDDATA              3          0                                 3011100300016 
ENDSUBENT           15          0                                 3011100399999 
ENDENTRY             3          0                                 3011199999999