ENTRY            40625   20180325                             41784062500000001 
SUBENT        40625001   20180325                             41784062500100001 
BIB                 12         35                                 4062500100002 
INSTITUTE  (4RUSFEI)                                              4062500100003 
REFERENCE  (J,AE,52,406,1982) Issue 6                             4062500100004 
           (J,SJA,52,403,1982) Engl.transl.of J,AE,52,406,1982    4062500100005 
AUTHOR     (A.A.Bergman,A.N.Medvedev,A.E.Samsonov,V.A.Tolstikov,  4062500100006 
           A.G.Kolosovskii,M.V.Mordovskii,A.Malikzhonov)          4062500100007 
TITLE      Measurement of the neutron radiative capture cross     4062500100008 
           section for 236U in the range of neutron energies      4062500100009 
           0.1 - 50. keV                                          4062500100010 
INC-SOURCE (D-T) Deuteron-tritium reaction, neutron pulse         4062500100011 
            0.5microsec, 960.Hz frequency                         4062500100012 
SAMPLE      Cylinder from (U)3(0)8,enrichment of U-236 is 99.84 %,4062500100013 
            net weight of U-236 is 6.477 gram, effective          4062500100014 
            thickness is 1.234E+21 nuclei/cm2                     4062500100015 
           Au sample (for normalization factor in graphite prism):4062500100016 
           identical geometrical form, 7.783g g, 1.81E+11 at/cm2 .4062500100017 
METHOD     (COINC,SLODT) Slowing-down of neutrons in lead         4062500100018 
DETECTOR   (PROPC)Gas proportional counter of special construction4062500100019 
            as reported by A.Bergman,A.E.,31,(2),107,1971         4062500100020 
           (SCIN) Scintillation detector with Ba(F)2 crystal      4062500100021 
MONITOR    (79-AU-197(N,G)79-AU-198,,SIG)  For EN=.025 eV         4062500100022 
            Westcott factor 1.005 for Au was used.                4062500100023 
PART-DET   (G) Gammas                                             4062500100024 
CORRECTION  Cross-section data were corrected for                 4062500100025 
            Sample admixtures (U-235, U-238),                     4062500100026 
            The recycled neutrons < 1.5%                          4062500100027 
            Shielding of neutron flux in SNM-3 boron counter 0.6%,4062500100028 
                 similar correction for Au sample 9.9%,           4062500100029 
            Deviation of B10(n,a) reaction CS from 1/v low < 4.%. 4062500100030 
            Instrumental resolution 0.4-05.%                      4062500100031 
HISTORY    (19820917C)                                            4062500100032 
           (20180325A) M.M. Upper -> lower case correction.       4062500100033 
           Dates were corrected for 4-digits year.                4062500100034 
           Ref.SJA,52,403,1982 was added.                         4062500100035 
           ERR-ANALYS was added. ERR-T -> DATA-ERR1,              4062500100036 
           DATA-ERR2 was added in DATA block.                     4062500100037 
ENDBIB              35          0                                 4062500100038 
COMMON               3          3                                 4062500100039 
EN-NRM     MONIT      MONIT-ERR                                   4062500100040 
EV         B          B                                           4062500100041 
 0.0253     98.8       0.3                                        4062500100042 
ENDCOMMON            3          0                                 4062500100043 
ENDSUBENT           42          0                                 4062500199999 
SUBENT        40625002   20180325                             41784062500200001 
BIB                  3         17                                 4062500200002 
REACTION   (92-U-236(N,G)92-U-237,,SIG,,AV) Over energy interval  4062500200003 
ERR-ANALYS (DATA-ERR1) Error includes all errors except           4062500200004 
           normalization error (ERR-2) and DATA-ERR2.             4062500200005 
           (DATA-ERR2) Includes intensities ratio and average     4062500200006 
           energy errors.                                         4062500200007 
           (ERR-1,,3.3) Intensities ratio error, mainly due to    4062500200008 
           statistics (80-90 %).                                  4062500200009 
           (ERR-2) Normalization error                            4062500200010 
           (ERR-3) Error due to regeneration of background        4062500200011 
           neutrons                                               4062500200012 
           (ERR-4,,0.2) Error due to increase of detection        4062500200013 
           efficiency for B-10(N,A) reaction                      4062500200014 
           (ERR-5,,0.2) Error due to U235 impurities in sample    4062500200015 
           (ERR-6,,1.1) Error due to time determination           4062500200016 
           (ERR-7,,1.9) Error due to determination of average     4062500200017 
           neutron energy                                         4062500200018 
STATUS     (TABLE) Table 1 of AE,52,406,1982                      4062500200019 
ENDBIB              17          0                                 4062500200020 
COMMON               2          3                                 4062500200021 
ERR-2      ERR-3                                                  4062500200022 
PER-CENT   PER-CENT                                               4062500200023 
 0.95       0.2                                                   4062500200024 
ENDCOMMON            3          0                                 4062500200025 
DATA                 5         25                                 4062500200026 
EN-MIN     EN-MAX     DATA       DATA-ERR1  DATA-ERR2             4062500200027 
KEV        KEV        B          PER-CENT   PER-CENT              4062500200028 
 1.0000E-01 1.5000E-01 9.797      2.2        1.9                  4062500200029 
 1.5000E-01 2.5000E-01 6.746      1.9        1.6                  4062500200030 
 2.5000E-01 3.0000E-01 5.694      1.7        1.4                  4062500200031 
 3.0000E-01 4.0000E-01 5.360      1.6        1.3                  4062500200032 
 4.0000E-01 5.0000E-01 5.196      1.6        1.3                  4062500200033 
 5.0000E-01 6.0000E-01 5.021      1.7        1.5                  4062500200034 
 6.0000E-01 7.0000E-01 4.794      1.7        1.4                  4062500200035 
 7.0000E-01 8.0000E-01 4.238      1.7        1.4                  4062500200036 
 8.0000E-01 9.0000E-01 3.686      1.8        1.6                  4062500200037 
 9.0000E-01 1.0000E+00 3.423      1.8        1.5                  4062500200038 
 1.0000E+00 2.0000E+00 2.475      1.5        1.2                  4062500200039 
 2.0000E+00 3.0000E+00 1.695      1.7        1.4                  4062500200040 
 3.0000E+00 4.0000E+00 1.398      2.0        2.0                  4062500200041 
 4.0000E+00 5.0000E+00 1.277      1.9        1.9                  4062500200042 
 5.0000E+00 6.0000E+00 1.154      2.1        2.1                  4062500200043 
 6.0000E+00 7.0000E+00 1.050      2.7        2.7                  4062500200044 
 7.0000E+00 8.0000E+00 0.9759     2.8        2.8                  4062500200045 
 8.0000E+00 9.0000E+00 0.9088     2.8        2.8                  4062500200046 
 9.0000E+00 1.0000E+01 0.8925     2.8        2.8                  4062500200047 
 1.0000E+01 1.5000E+01 0.7995     2.0        2.0                  4062500200048 
 1.5000E+01 2.0000E+01 0.6685     2.4        2.4                  4062500200049 
 2.0000E+01 2.5000E+01 0.5832     3.2        3.2                  4062500200050 
 2.5000E+01 3.0000E+01 0.5724     3.2        3.2                  4062500200051 
 3.0000E+01 4.0000E+01 0.4977     3.2        3.2                  4062500200052 
 4.0000E+01 5.0000E+01 0.4276     3.4        3.4                  4062500200053 
ENDDATA             27          0                                 4062500200054 
ENDSUBENT           53          0                                 4062500299999 
ENDENTRY             2          0                                 4062599999999