ENTRY            40011   20141114                             41674001100000001 
SUBENT        40011001   20141114                             41674001100100001 
BIB                 15         56                                 4001100100002 
TITLE       On variation of the kinetic energy of the fragments   4001100100003 
           from 92-U-235 fission by 0.15-1.68 MeV neutrons        4001100100004 
AUTHOR     (E.Dermendzhiev, N.Kashukeev, Ts.Panteleev,            4001100100005 
           Tyan San Khak)                                         4001100100006 
INSTITUTE  (4ZZZDUB)                                              4001100100007 
REFERENCE  (R,JINR-P3-4873,196912)                                4001100100008 
REL-REF    (I,,S.Bochvarov+,R,JINR-P3-4110,1968)                  4001100100009 
           (I,,V.Z.Mikhaylova+,J,NIM,66,25,1968)                  4001100100010 
MONITOR     No information.                                       4001100100011 
           Absolute counting of fission events.                   4001100100012 
COMMENT    Of compiler M.M.                                       4001100100013 
           Initially, this MONITOR was compiled in 1970 by reactio4001100100014 
             (U-235(N,F),,DE,FF,REL)=1. .                         4001100100015 
            In 2014 reaction is                                   4001100100016 
             "(U-235(N,F),,AKE,FF) =1. at thermal fission" ,      4001100100017 
            what is wrong, because AKE,FF at thermal fission is   4001100100018 
           about 170 MeV (TKE) .                                  4001100100019 
FACILITY   (VDG,4ZZZDUB)      Van de Graaff EG-5                  4001100100020 
            Proton current ~20-30 microA.                         4001100100021 
INC-SOURCE (P-LI7)   Thickness of Li target is 0.38 mg/cm2,       4001100100022 
                     diameter is equal to 1cm .                   4001100100023 
            Energy resolution at all points is about 0.08 MeV.    4001100100024 
            For fast neutrons in 0.15 MeV - 1.68 MeV energy range.4001100100025 
            - Thermal neutrons were obtained by slowing-down in   4001100100026 
           paraffin block.                                        4001100100027 
SAMPLE     Two samples in ionization chamber. Diameter 9.2 cm .   4001100100028 
           Thickness ~ 1.8 mg/cm2 .                               4001100100029 
METHOD     (FISCT)                                                4001100100030 
           Cyclic measurements at fast and thermal neutron beams  4001100100031 
           about 30 min at each beam.                             4001100100032 
           2PI geometry in combination with samples rotation at   4001100100033 
           45 deg to avoid influence from angular anisotropy of   4001100100034 
           fission fragments.                                     4001100100035 
PART-DET   (FF)       Fission-fragments                           4001100100036 
DETECTOR   (FISCH) Double ionization fission chamber.             4001100100037 
           Registration discrimination thresholds 55-60 MeV and   4001100100038 
           20 MeV.                                                4001100100039 
ERR-ANALYS (DATA-ERR) Standard deviation.                         4001100100040 
HISTORY    (19700619R)                                            4001100100041 
           (19700619C)                                            4001100100042 
           (19830303A)  corrected in BNL                          4001100100043 
           (19971214A)  corrected in CJD                          4001100100044 
           (20141114A) SD: Updated to new date formats,lower case.4001100100045 
            Code in METHOD deleted. SF6=KE -> AKE in MONITOR and  4001100100046 
            REACTION code according to EXFOR rules in Subents 1-3.4001100100047 
           (20141223A) M.M. The article was checked,              4001100100048 
           BIB information was updated in FACILITY,INC-SOURCE,    4001100100049 
           METHOD,SAMPLE,DETECTOR,ERR-ANALYS,ANALYSIS,STATUS,     4001100100050 
           REL-REF,EN-SEC,COMMENTs.                               4001100100051 
           MONITOR was deleted as wrong - see COMMENT of compiler.4001100100052 
           Reaction was corrected (see ANALYSIS in Subent 002) :  4001100100053 
             (92-U-235(N,F),,AKE,FF,REL) ->                       4001100100054 
             ((92-U-235(N,F),PAR/PRE,FY,,REL/MSC)//               4001100100055 
             (92-U-235(N,F),PAR/PRE,FY,,REL/MSC)) .               4001100100056 
           EN -> EN-NM; E1-MIN,E2-MIN, EN-DN, EN-SEC were added.  4001100100057 
           ARB-UNITS -> NO-DIM .                                  4001100100058 
ENDBIB              56          0                                 4001100100059 
COMMON               1          3                                 4001100100060 
EN-RSL-FW                                                         4001100100061 
MEV                                                               4001100100062 
 0.08                                                             4001100100063 
ENDCOMMON            3          0                                 4001100100064 
ENDSUBENT           63          0                                 4001100199999 
SUBENT        40011002   20141114                             41674001100200001 
BIB                  6         45                                 4001100200002 
REACTION   ((92-U-235(N,F),PAR/PRE,FY,,MSC)//                     4001100200003 
           (92-U-235(N,F),PAR/PRE,FY,,MSC))                       4001100200004 
            See ANALYSIS for explanation of measured quantity.    4001100200005 
ANALYSIS    Relative yield W of fission fragments was defined as: 4001100200006 
           W=(N1fast/N2fast)/(N1thermal/N2thermal),               4001100200007 
           N1 - number of counts in 1st sample with high          4001100200008 
           discrimination threshold E1=55-60 MeV,                 4001100200009 
           N2 - number of counts in 2nd sample with low           4001100200010 
           discrimination threshold E2=20 MeV; corrected for      4001100200011 
           backgrounds due to alpha-particles                     4001100200012 
            ( average background ~ 2count/min).                   4001100200013 
           fast - for fast neutrons,                              4001100200014 
           thermal - for thermal neutrons.                        4001100200015 
           Maximal counts rate in measurement at thermal neutrons 4001100200016 
            about 200 count/sec.                                  4001100200017 
EN-SEC     (E1-MIN,FF) High discrimination threshold E1=55-60 MeV.4001100200018 
           (E2-MIN,FF) Low discrimination threshold E2=20 MeV.    4001100200019 
COMMENT    Of compiler M.M.                                       4001100200020 
           On Fig.1 these data are given in two Y scales:         4001100200021 
           left - W ( see ANALYSIS), right - deltaEk, where       4001100200022 
           deltaEk - average deviation of fission fragments       4001100200023 
             kinetic energy at fission by fast neutrons EKfast    4001100200024 
             from one at fission by thermal neutrons EKthermal,   4001100200025 
             EKfast-EKthermal.                                    4001100200026 
            Scale values correspondence:                          4001100200027 
           W,no-dim   deltaEk,MeV                                 4001100200028 
           0.96       -0.8                                        4001100200029 
           0.98       -0.4                                        4001100200030 
           1.00       0.                                          4001100200031 
           1.02       0.4                                         4001100200032 
           1.04       0.8                                         4001100200033 
           So, to define deltaEk (MeV) from W values (no-dim),    4001100200034 
           a formula could be applied:                            4001100200035 
           deltaEk= (W-1.)*20  .                                  4001100200036 
STATUS     (PRELM) Preliminary measurement.                       4001100200037 
           (TABLE) Table 1 of R,JINR-P3-4873,1969 .               4001100200038 
HISTORY    (19971214A)   Reaction quantity corrected              4001100200039 
           (20141114A) SD:  SF6=KE -> AKE in REACTION code        4001100200040 
            according to EXFOR rules.                             4001100200041 
           (20141223A) M.M. Reaction was corrected                4001100200042 
             (92-U-235(N,F),,AKE,FF,REL) ->                       4001100200043 
             ((92-U-235(N,F),PAR/PRE,FY,,REL/MSC)//               4001100200044 
             (92-U-235(N,F),PAR/PRE,FY,,REL/MSC)) .               4001100200045 
           EN -> EN-NM; E1-MIN,E2-MIN, EN-DN, EN-SEC were added.  4001100200046 
           ARB-UNITS -> NO-DIM .                                  4001100200047 
ENDBIB              45          0                                 4001100200048 
COMMON               3          3                                 4001100200049 
EN-DN      E1-MIN     E2-MIN                                      4001100200050 
EV         MEV        MEV                                         4001100200051 
0.0253       55.       20.                                        4001100200052 
ENDCOMMON            3          0                                 4001100200053 
DATA                 3          4                                 4001100200054 
EN-NM      DATA       DATA-ERR                                    4001100200055 
MEV        NO-DIM     NO-DIM                                      4001100200056 
 1.5       0.995      0.026                                       4001100200057 
 4.3       1.005      0.020                                       4001100200058 
 7.7       1.020      0.019                                       4001100200059 
 9.9       1.005      0.023                                       4001100200060 
ENDDATA              6          0                                 4001100200061 
ENDSUBENT           60          0                                 4001100299999 
SUBENT        40011003   20141114                             41674001100300001 
BIB                  5         12                                 4001100300002 
REACTION   ((92-U-235(N,F),PAR/PRE,FY,,MSC)//                     4001100300003 
           (92-U-235(N,F),PAR/PRE,FY,,MSC))                       4001100300004 
           See ANALYSIS for explanation of measured quantity,     4001100300005 
           in this Subent and in Subent 002.                      4001100300006 
ANALYSIS    Data are averaged on several measurements             4001100300007 
            See also ANALYSIS in Subent 002 for data definition.  4001100300008 
EN-SEC     (E1-MIN,FF) High discrimination threshold E1=55-60 MeV.4001100300009 
           (E2-MIN,FF) Low discrimination threshold E2=20 MeV.    4001100300010 
STATUS     (TABLE) Table 1 of R,JINR-P3-4873,1969 .               4001100300011 
HISTORY    (19971214A)   Reaction quantity corrected              4001100300012 
           (20141114A) SD:  SF6=KE -> AKE in REACTION code        4001100300013 
            according to EXFOR rules.                             4001100300014 
ENDBIB              12          0                                 4001100300015 
COMMON               3          3                                 4001100300016 
EN-DN      E1-MIN     E2-MIN                                      4001100300017 
EV         MEV        MEV                                         4001100300018 
0.0253       55.       20.                                        4001100300019 
ENDCOMMON            3          0                                 4001100300020 
DATA                 3         14                                 4001100300021 
EN-NM      DATA       DATA-ERR                                    4001100300022 
MEV        NO-DIM     NO-DIM                                      4001100300023 
 0.26       1.000      0.006                                      4001100300024 
 0.37       0.991      0.005                                      4001100300025 
 0.49       1.002      0.004                                      4001100300026 
 0.59       0.999      0.004                                      4001100300027 
 0.71       1.009      0.006                                      4001100300028 
 0.77       1.018      0.009                                      4001100300029 
 0.81       1.016      0.006                                      4001100300030 
 0.88       0.998      0.008                                      4001100300031 
 0.99       0.996      0.008                                      4001100300032 
 1.09       1.006      0.008                                      4001100300033 
 1.21       1.014      0.008                                      4001100300034 
 1.38       1.011      0.010                                      4001100300035 
 1.58       1.013      0.008                                      4001100300036 
 1.68       1.018      0.010                                      4001100300037 
ENDDATA             16          0                                 4001100300038 
ENDSUBENT           37          0                                 4001100399999 
ENDENTRY             3          0                                 4001199999999