ENTRY            41065   20240913                             42194106500000001 
SUBENT        41065001   20240913                             42194106500100001 
BIB                 10         18                                 4106500100002 
TITLE       Long-living 209Po in Bi-209 neutron-irradiation       4106500100003 
           products                                               4106500100004 
AUTHOR     (S.L.Faddeev,G.I.Antonov,Yu.S.Egorov,A.V.Mozzhukhin,   4106500100005 
           Yu.L.Chereshkevich)                                    4106500100006 
REFERENCE  (J,SJA,68,235,1990)   English translation              4106500100007 
           (J,AE,68,203,1990) Issue 3.                            4106500100008 
INSTITUTE  (4RUSKUR)                                              4106500100009 
FACILITY   (REAC,4RUSKUR)                                         4106500100010 
INC-SPECT   Thermal neutron spectrum of reactor.                  4106500100011 
           Mean flux density 1.E+13 n/cm2/sec.                    4106500100012 
DETECTOR   (GELI) Resolution 20 keV                               4106500100013 
MONITOR     No information.                                       4106500100014 
ERR-ANALYS  Error is not given                                    4106500100015 
HISTORY    (19920318C)  + + Compiled at the centre - CJD + +      4106500100016 
           (19930217A)  SAN 003 was deleted due to reaction code  4106500100017 
                      repetition                                  4106500100018 
           (20240913A) Subent 002 was corrected.                  4106500100019 
            BIB information was updated.                          4106500100020 
ENDBIB              18          0                                 4106500100021 
COMMON               1          3                                 4106500100022 
EN-DUMMY                                                          4106500100023 
EV                                                                4106500100024 
   2.53E-02                                                       4106500100025 
ENDCOMMON            3          0                                 4106500100026 
ENDSUBENT           25          0                                 4106500199999 
SUBENT        41065002   20240913                             42194106500200001 
BIB                  7         18                                 4106500200002 
REACTION   (84-PO-210(N,2N)84-PO-209,,SIG,,SPA)                   4106500200003 
DECAY-DATA (84-PO-210,138.4D)                                     4106500200004 
           (84-PO-209,103.YR,A,4880.,,DG,262.,,DG,893.)           4106500200005 
SAMPLE      Po heat sources made in 1972-1973, containing at time 4106500200006 
           of manufacture (1.5 - 2.8)*10**8 MBq (4000-7600 Ci) of 4106500200007 
           Po-210.                                                4106500200008 
METHOD      Irradiation during 200 days. 209Po/210Po activity     4106500200009 
           ratio at the end of irradiation 1.3E-10.               4106500200010 
ANALYSIS   Reaction threshold was estimated to be close to 7.7MeV.4106500200011 
           Effective flux density was 1.E+11 n/cm2/sec for this   4106500200012 
           reaction may deviate by up to factor 10 from the value 4106500200013 
           assumed. So with adequate accuracy the cross section   4106500200014 
           for the formation of Po-209 in Po-210(n,2n) is in the  4106500200015 
           range 0.1 - 0.001 b.                                   4106500200016 
STATUS     (TABLE,,S.L.Faddeev+,J,SJA,68,235,1990) Text page 236  4106500200017 
HISTORY    (20240913A) DATA -> DATA-APR.                          4106500200018 
           SPA code was added in REACTION.                        4106500200019 
           DECAY-DATA were added.                                 4106500200020 
ENDBIB              18          0                                 4106500200021 
NOCOMMON             0          0                                 4106500200022 
DATA                 1          1                                 4106500200023 
DATA-APRX                                                         4106500200024 
MB                                                                4106500200025 
   14.                                                            4106500200026 
ENDDATA              3          0                                 4106500200027 
ENDSUBENT           26          0                                 4106500299999 
NOSUBENT      41065003   20240913                             42194106500300001 
ENDENTRY             3          0                                 4106599999999