ENTRY            40431   20220228                             42044043100000001 
SUBENT        40431001   20220228                             42044043100100001 
BIB                 11         47                                 4043100100002 
TITLE       Absolute measurements of the radiative capture        4043100100003 
            cross section of 238U for 30 keV neutrons             4043100100004 
AUTHOR     (Yu.G.Panitkin,L.E.Sherman)                            4043100100005 
REFERENCE  (J,SJA,39,591,1975) Eng.trans.of AE,39,17,1975         4043100100006 
           (J,AE,39,17,1975) Issue 1. Data are given              4043100100007 
           (R,YFI-19,7,1974)     Data are given                   4043100100008 
           (R,INDC(CCP)-65,4,1975)                                4043100100009 
           Engl.translation of YFI-19,p.7,1974                    4043100100010 
INSTITUTE  (4RUSFEI)                                              4043100100011 
INC-SOURCE (P-LI7) Maximum proton energy equal 2.5 MeV.           4043100100012 
METHOD     (ACTIV)  Activation method for definition              4043100100013 
            of neutron radiative capture cross-section.           4043100100014 
            Method of associated activity over gamma-rays with    4043100100015 
            energy 477 keV from reaction Li-7(p,n)Be-7            4043100100016 
            for definition of neutron flux.                       4043100100017 
FACILITY   (VDG,4RUSFEI)                                          4043100100018 
DETECTOR   (GELI)  Germanium-lithium detector for measurement     4043100100019 
           of U-239 activity. 4PI-beta-counter was used for       4043100100020 
           definition of GeLi-detection efficiency.               4043100100021 
           (FISCH,BF3) U-235 fission chamber and long BF3 counter 4043100100022 
           were used for neutron beam monitoring.                 4043100100023 
CORRECTION Resonance self-shielding (0.3%),                       4043100100024 
           multiple neutron scattering in target (0.3%),          4043100100025 
           background of neutrons scattering in chamber           4043100100026 
           of Li-7 target (0.1%), neutron scattering              4043100100027 
           by materials of construction (5.0%),                   4043100100028 
           effective thickness of target-sample because of        4043100100029 
           apex angle of neutron cone (1.3%)                      4043100100030 
ERR-ANALYS (ERR-T) Error shown on the data is total and includes  4043100100031 
           (ERR-S) statistical error of one measurement (1.5%),   4043100100032 
           (ERR-1) Ge(Li)-detector efficiency error for           4043100100033 
           measurement of U-238 - 2.1%                            4043100100034 
           (ERR-2) Ge(Li)-detector efficiency error for           4043100100035 
           measurement of Li-target - 3.38%,                      4043100100036 
           (ERR-3) self-shielding error (0.1%),                   4043100100037 
           (ERR-4) neutron flux error (0.2%),                     4043100100038 
           (ERR-5) neutron scattering error (0.15%),              4043100100039 
           (ERR-6) half-life error of U-239 and Be-7 (0.5%)       4043100100040 
HISTORY    (19770215C)                                            4043100100041 
           (19870609A) Renormalized data deleted. ISO-QUANT into  4043100100042 
                      REACTION converted.                         4043100100043 
           (20150218U) SD: Updated to new date formats,lower case.4043100100044 
             Ref. on Engl.transl. of AE added. ERR-ANALYS updated.4043100100045 
           (20170306U) M.M. Article was checked, BIB information  4043100100046 
            was corrected in SAMPLE,DECAY-DATA,DETECTOR,          4043100100047 
           (20220228A) Ref.INDC(CCP)-65,4,1975 was added.         4043100100048 
           Minor correction of free text.                         4043100100049 
ENDBIB              47          0                                 4043100100050 
COMMON               7          6                                 4043100100051 
ERR-S      ERR-1      ERR-2      ERR-3      ERR-4      ERR-5      4043100100052 
ERR-6                                                             4043100100053 
PER-CENT   PER-CENT   PER-CENT   PER-CENT   PER-CENT   PER-CENT   4043100100054 
PER-CENT                                                          4043100100055 
  0.3         2.1        3.38      0.1        0.2         0.15    4043100100056 
  0.5                                                             4043100100057 
ENDCOMMON            6          0                                 4043100100058 
ENDSUBENT           57          0                                 4043100199999 
SUBENT        40431002   20220228                             42044043100200001 
BIB                  6         10                                 4043100200002 
REACTION   (92-U-238(N,G)92-U-239,,SIG)                           4043100200003 
DECAY-DATA (92-U-239,,DG,74.)                                     4043100200004 
SAMPLE      U238 uranous-uranic oxide U(3)O(8), 300 mg/cm2        4043100200005 
            thickness.                                            4043100200006 
COMMENT     Data from this Subent transferred to subent 40177003  4043100200007 
             ( in 40177003 - data at 24keV-7MeV range renormalized4043100200008 
             by author in 1987)                                   4043100200009 
STATUS     (TABLE) Tbl. I of At.Energy,v.39,p.17,1975             4043100200010 
           (SPSDD,40177003) See comment.                          4043100200011 
HISTORY    (20220228A) (SPSDD,40144003) -> (SPSDD,40177003)       4043100200012 
ENDBIB              10          0                                 4043100200013 
NOCOMMON             0          0                                 4043100200014 
DATA                 4          1                                 4043100200015 
EN         EN-ERR     DATA       ERR-T                            4043100200016 
KEV        KEV        MB         MB                               4043100200017 
  30.        6.         465.       23.                            4043100200018 
ENDDATA              3          0                                 4043100200019 
ENDSUBENT           18          0                                 4043100299999 
ENDENTRY             2          0                                 4043199999999