ENTRY            40423   20210220                             41954042300000001 
SUBENT        40423001   20210220                             41954042300100001 
BIB                 10         38                                 4042300100002 
INSTITUTE  (4RUSLIN)                                              4042300100003 
REFERENCE  (J,YF,17,703,1973) Issue 4. Figures only.              4042300100004 
           (J,SNP,17,366,1973) Engl.transl.of J,YF,17,703,1973    4042300100005 
           (J,YF,18,720,1973) Issue 4. Figures only.              4042300100006 
           (J,SNP,18,369,1974) Engl.translation of YF,18,720,1973 4042300100007 
AUTHOR     (A.P.Graevsky,B.A.Bochagov,Yu.A.Chestnov)              4042300100008 
TITLE       Angular neutron distribution from triple fission      4042300100009 
            of Cf-252                                             4042300100010 
METHOD     (COINC)  N-alpha coincidence                           4042300100011 
           (TOF) Neutron energy was measured by time-of-flight.   4042300100012 
           Start signal from alpha, stop - from neutron detector. 4042300100013 
SAMPLE      Cf-252 source of 5 mm diameter on Pt backing.         4042300100014 
DETECTOR   (COIN,SCIN,SOLST) Plastic scintillation detector of    4042300100015 
           150 mm diameter, 150 mm length, with photomultiplier   4042300100016 
           FEU-65, distance from Cf252 sample 0.5 m -for neutrons;4042300100017 
           semiconductor detector of 20x20 mm**2, distance from Cf4042300100018 
           source 27 mm - for alphas .                            4042300100019 
           Neutron detector efficiency was defined by spectrum of 4042300100020 
           Cf-252 binary fission, time resolution +-2.5 nsec.     4042300100021 
MONITOR     Relative measurements                                 4042300100022 
MISC-COL   (MISC)      Maximal statistical error.                 4042300100023 
           Stat.errors do not exceed the size of points on figure.4042300100024 
HISTORY    (19781031C)  Compiled at the centre                    4042300100025 
           (19840228U)  Minor errors corrected                    4042300100026 
           (20130620A) M.M. Upper -> lower case correction.       4042300100027 
           Dates were corrected for 4-digits year.                4042300100028 
           INC-SOURCE line was deleted (spon.fission).            4042300100029 
           Ref.of Engl.translation was added.                     4042300100030 
           BIB information was updated.                           4042300100031 
           Authors list and TITLE were corrected as given in      4042300100032 
           abstract of J,YF,17,(4),703,1973.                      4042300100033 
           ANG1 -> ANG-RL . DA,N -> NU/DA,, .                     4042300100034 
           Max. stat.error ERR-S is moved from ERR-ANALYS in MISC 4042300100035 
           according to comment of N.Otsuka (NDS,IAEA).           4042300100036 
           (20200922A) Refs. YF,18,720,1973 and Engl.translation  4042300100037 
            were added.                                           4042300100038 
            REACTION was corrected in Subent 002.                 4042300100039 
           (20210220A) Reaction was corrected in Subent 002.      4042300100040 
ENDBIB              38          0                                 4042300100041 
NOCOMMON             0          0                                 4042300100042 
ENDSUBENT           41          0                                 4042300199999 
SUBENT        40423002   20210220                             41954042300200001 
BIB                  5         15                                 4042300200002 
REACTION   (98-CF-252(0,F),TER,DA,N,MSC)  Angular distribution    4042300200003 
            of emitted neutrons relative to the emitted ternary   4042300200004 
            fission alpha-particles. In arbitrary units.          4042300200005 
                    ANG-RL value in DATA section is angle between 4042300200006 
            alpha and neutron directions.                         4042300200007 
CORRECTION  Geometrical correction was made.                      4042300200008 
ADD-RES     In Yad.Fiz.,v.18,is.4,p.720,1973, text page 721 :     4042300200009 
            Average neutron energy 4.6+-0.3 MeV is given for      4042300200010 
           difference of two TOF spectra for 0 deg - 180 deg angle4042300200011 
           of alpha-particles in ternary fission.                 4042300200012 
STATUS     (CURVE) Fig.3 of Yad.Fiz.,v.17,is.4,p.703,1973.        4042300200013 
                   Fig.1 of Yad.Fiz.,v.18,is.4,p.720,1973         4042300200014 
HISTORY    (20200922U) ADD-RES was added.                         4042300200015 
           (20210220A) DA,N, -> DA,N+A,                           4042300200016 
                       REL -> MSC                                 4042300200017 
ENDBIB              15          0                                 4042300200018 
NOCOMMON             0          0                                 4042300200019 
DATA                 3         10                                 4042300200020 
ANG-RL     DATA       MISC                                        4042300200021 
ADEG       ARB-UNITS  ARB-UNITS                                   4042300200022 
 0.0000E+00 6.7000E-01 5.0000E-02                                 4042300200023 
 1.5000E+01 7.4000E-01 5.0000E-02                                 4042300200024 
 4.6000E+01 1.0000E+00 5.0000E-02                                 4042300200025 
 7.7000E+01 1.2400E+00 5.0000E-02                                 4042300200026 
 9.3000E+01 1.2700E+00 5.0000E-02                                 4042300200027 
 1.0900E+02 1.1700E+00 5.0000E-02                                 4042300200028 
 1.1800E+02 1.0400E+00 5.0000E-02                                 4042300200029 
 1.3600E+02 7.2000E-01 5.0000E-02                                 4042300200030 
 1.7300E+02 4.8000E-01 5.0000E-02                                 4042300200031 
 1.8000E+02 4.8000E-01 5.0000E-02                                 4042300200032 
ENDDATA             12          0                                 4042300200033 
ENDSUBENT           32          0                                 4042300299999 
ENDENTRY             2          0                                 4042399999999