ENTRY            30209   20130131                             31583020900000001 
SUBENT        30209001   20130131                             31583020900100001 
BIB                 13         32                                 3020900100002 
INSTITUTE  (3RUMBUC,4ZZZDUB)                                      3020900100003 
REFERENCE  (J,NP/A,97,444,196704)                                 3020900100004 
           (R,IFA-CRD-32,196612)                                  3020900100005 
AUTHOR     (G.N.Flerov,A.A.Pleve,S.M.Polikanov,S.P.Tretyakova,    3020900100006 
           N.Martalogu,D.Poenaru,M.Sezon,I.Vilcov,N.Vilcov)       3020900100007 
TITLE      Excitation energy of spontaneously fissioning          3020900100008 
           isomer 242(m)-Am.                                      3020900100009 
FACILITY   (CYCLO,4ZZZDUB)  Cyclotron, pulsed operation           3020900100010 
INC-SOURCE (D-D)    D(d,n)He-3 reaction,  gaseous D-target        3020900100011 
METHOD     (ACTIV)    Activation, pulsed n-beam of 28 msec length 3020900100012 
           in 56msec intervals between pulses detection of        3020900100013 
           isomeric fission                                       3020900100014 
DETECTOR   12 fission fragments mica detectors rotating before    3020900100015 
           the target synchronized with the cyclotron             3020900100016 
PART-DET   (FF) fission fragments                                 3020900100017 
COMMENT    The neutron energy corresponding to the reaction       3020900100018 
           threshold was found to be 9.2 +- 0.3 MeV in C.M.System 3020900100019 
           The difference between this value and the threshold    3020900100020 
           of the reaction leading to the ground state is         3020900100021 
           considered as the excitation energy of the spontaneous-3020900100022 
           ly fissioning state of 242-Am.                         3020900100023 
           Excitation energy = 2.9 +- 0.4 MeV                     3020900100024 
STATUS     (TABLE)  Data from publication NP/A 97 444 Table 1.    3020900100025 
           (APRVD) Approved by Vilcov (19731010)                  3020900100026 
HISTORY    (19721121T)  Conversion of DASTAR 694.                 3020900100027 
           (19730615A)                                            3020900100028 
           (20080211A) BIB section updated                        3020900100029 
           (20121228A) VS REACTION code and DECAY-DATA corrected. 3020900100030 
ERR-ANALYS Largest part of errors is due to counting statistics.  3020900100031 
           Errors also due to  uncertainties in the determination 3020900100032 
           of the neutron flux, the efficiency of fission fragment3020900100033 
           detection and the amount of 243-Am in the target.      3020900100034 
ENDBIB              32          0                                 3020900100035 
NOCOMMON             0          0                                 3020900100036 
ENDSUBENT           35          0                                 3020900199999 
SUBENT        30209002   20130131                             31583020900200001 
BIB                  2          2                                 3020900200002 
REACTION   (95-AM-243(N,2N)95-AM-242-L,,SIG)                      3020900200003 
DECAY-DATA (95-AM-242-L,14.0MSEC) A half-life of 14.0 +- 0.7 msec.3020900200004 
ENDBIB               2          0                                 3020900200005 
COMMON               1          3                                 3020900200006 
ERR-HL                                                            3020900200007 
MSEC                                                              3020900200008 
 7.0000E-01                                                       3020900200009 
ENDCOMMON            3          0                                 3020900200010 
DATA                 2         11                                 3020900200011 
EN         DATA                                                   3020900200012 
MEV        MICRO-B                                                3020900200013 
 8.          3.                                                   3020900200014 
 9.4         2.                                                   3020900200015 
 9.4         2.4                                                  3020900200016 
10.2        20.                                                   3020900200017 
10.5        52.                                                   3020900200018 
11.2        94.                                                   3020900200019 
11.5       130.                                                   3020900200020 
12.8       130.                                                   3020900200021 
13.0       130.                                                   3020900200022 
14.2       140.                                                   3020900200023 
14.4        76.                                                   3020900200024 
ENDDATA             13          0                                 3020900200025 
ENDSUBENT           24          0                                 3020900299999 
ENDENTRY             2          0                                 3020999999999