ENTRY            40701   20210312                             41954070100000001 
SUBENT        40701001   20210312                             41954070100100001 
BIB                 17         76                                 4070100100002 
TITLE       Measurement of the cross sections of the reaction     4070100100003 
           237Np(n,2n)236Np (22.5 h) for neutron energies in the  4070100100004 
           range 7-10 MeV                                         4070100100005 
AUTHOR     (N.V.Kornilov,V.Ya.Baryba,A.V.Balitskii,A.P.Rudenko,   4070100100006 
           B.D.Kuz'minov,O.A.Sal'nikov,                           4070100100007 
           E.A.Gromova,S.S.Kovalenko,L.D.Preobrazhenskaya,        4070100100008 
           A.V.Stepanov,Yu.A.Nemilov,Yu.A.Selitskii,B.I.Tarler,   4070100100009 
           V.B.Funshtein,V.A.Yakovlev,                            4070100100010 
           Sh.Darotsi,P.Raich,I.Chikai)                           4070100100011 
           Sh.Darotsi = S.Daroczy; P.Raich = P.Raics,             4070100100012 
           I.Chikai = J.Csikai                                    4070100100013 
INSTITUTE  (4RUSFEI)  First six authors                           4070100100014 
           (4RUSRI)   Nine following authors                      4070100100015 
           (3HUNKOS)  Three last authors                          4070100100016 
REFERENCE  (J,AE,58,117,1985) Issue 2.                            4070100100017 
           (J,SJA,58,131,1985)                                    4070100100018 
           #doi:10.1007/BF01122203                                4070100100019 
            Engl.transl.of At.Energy,v.58,is.2,p.117,1985         4070100100020 
           (S,IAEA-TECDOC-336,305,1985) in English                4070100100021 
REL-REF    (M,30561001,N.V.Kornilov+,J,AE,49,283,1980) Issue 5.   4070100100022 
           Kornilov et.al, experimental details. U8(n,2n).        4070100100023 
           (M,30561001,N.V.Kornilov+,J,SJA,49,722,1980)           4070100100024 
           Engl.translation of At.Energy,v.49,is.5,p.283,1980.    4070100100025 
FACILITY   (VDGT,4RUSFEI) Charge exchange accelerator EGM-10M.    4070100100026 
INC-SOURCE (D-D)                                                  4070100100027 
MONITOR     Three monitors for neutron flux.                      4070100100028 
          1(13-AL-27(N,A)11-NA-24,,SIG)                           4070100100029 
          2(92-U-238(N,F),,SIG)                                   4070100100030 
          3(92-U-238(N,2N)92-U-237,,SIG)                          4070100100031 
MONIT-REF 1(,B.Magurno,R,IAEA-208,375,1978)                       4070100100032 
                                            ENDF/B-V dosim.file   4070100100033 
          2(,N.V.Kornilov,J,YK,,(1/45),33,1982)                   4070100100034 
          3(,B.Magurno,R,IAEA-208,375,1978)                       4070100100035 
                                            ENDF/B-V dosim.file   4070100100036 
DETECTOR   (GELI) For gamma detection                             4070100100037 
           (SCIN) Scintillation layer counter for beta detection  4070100100038 
PART-DET   (DG)   Decay gamma of 237U and 24Na                    4070100100039 
           (B-)   Beta-minus of 24Na                              4070100100040 
SAMPLE      Np-oxide placed in thin-walled containers of 10 mm    4070100100041 
           diameter, 2-3 mm height. Samples weight 140-400 mg.    4070100100042 
           Np was prepurified from Pu isotopes by a factor of     4070100100043 
           about 10**5. Background of Pu-236 was within 0.1% of   4070100100044 
           the induced one.                                       4070100100045 
METHOD     (ACTIV,CHSEP) Each sample was irradiated for 80-100 hr.4070100100046 
           Np-236 decays to Pu-236 by beta(-) emission.           4070100100047 
           Cross section for Np-237(n,2n)Np-236 reaction was      4070100100048 
           measured by detection of alpha particle emission       4070100100049 
           from Pu-236.                                           4070100100050 
           After irradiation,Pu-236 was radiochemically separated.4070100100051 
           For this purpose, Pu-239 was used as tracer and        4070100100052 
           the cross section was calculated by formula            4070100100053 
            sigma(n,2n)=A*(n(Pu-236)/n(Pu-239))*(1/(N*f*l*W))     4070100100054 
            where                                                 4070100100055 
           A- Pu-239 activity                                     4070100100056 
           n(Pu-236)/n(Pu-239) - ratio of alpha intensities from  4070100100057 
                                Pu-236 and Pu-239                 4070100100058 
           N- number of Np-237 nuclei in the sample               4070100100059 
           f- neutron flux                                        4070100100060 
           l- decay constant for Pu-236                           4070100100061 
           W- beta(-) decay probability for Np-236 = 0.48+-0.01   4070100100062 
CORRECTION   Correction on neutron flux fluctuations < 10% .      4070100100063 
ERR-ANALYS (ERR-T) uncertainty includes:                          4070100100064 
           (ERR-1,,4.) Flux determination                         4070100100065 
           (ERR-2) Uncertainty in the number of Np-237 nuclei     4070100100066 
           (ERR-3) Uncertainty of Pu-239 activity                 4070100100067 
           (ERR-4,,3.) Uncertainty in the ratio of alpha-particles4070100100068 
                 from Pu-236 and Pu-239                           4070100100069 
           (ERR-5) Error of beta(-) branching ratio               4070100100070 
STATUS     (APRVD) N.Kornilov, 1984-07-12                         4070100100071 
                            Entry 40701 supersedes 30817 .        4070100100072 
HISTORY    (19840713C) Compiled at CJD .                          4070100100073 
           (20140725S) Entry was restored.                        4070100100074 
           Upper -> lower case correction.                        4070100100075 
           Dates were corrected for 4-digits year.                4070100100076 
           BIB information was updated.                           4070100100077 
           (20210312U) Subent 002 was corrected.                  4070100100078 
ENDBIB              76          0                                 4070100100079 
COMMON               3          3                                 4070100100080 
ERR-2      ERR-3      ERR-5                                       4070100100081 
PER-CENT   PER-CENT   PER-CENT                                    4070100100082 
   0.8        1.0       2.0                                       4070100100083 
ENDCOMMON            3          0                                 4070100100084 
ENDSUBENT           83          0                                 4070100199999 
SUBENT        40701002   20210312                             41954070100200001 
BIB                  5          5                                 4070100200002 
REACTION   (93-NP-237(N,2N)93-NP-236-M,,SIG)                      4070100200003 
DECAY-DATA (93-NP-236-M,22.5HR,B-,,0.48)                          4070100200004 
RAD-DET    (94-PU-236,A)                                          4070100200005 
STATUS     (TABLE) At.Energy,v.58,is.2,p.117,1985                 4070100200006 
HISTORY    (20210212U) Comma was added in DECAY-DATA              4070100200007 
ENDBIB               5          0                                 4070100200008 
COMMON               1          3                                 4070100200009 
ERR-HL                                                            4070100200010 
HR                                                                4070100200011 
 0.4                                                              4070100200012 
ENDCOMMON            3          0                                 4070100200013 
DATA                 5          7                                 4070100200014 
EN         EN-ERR     EN-RSL-FW  DATA       ERR-T                 4070100200015 
MEV        MEV        MEV        MB         MB                    4070100200016 
 7.09       .10        .46         49.        3.                  4070100200017 
 7.47       .10        .50         86.        4.                  4070100200018 
 7.90       .09        .47        123.        7.                  4070100200019 
 8.32       .11        .55        191.        9.                  4070100200020 
 8.90       .11        .56        256.       13.                  4070100200021 
 9.37       .12        .56        338.       13.                  4070100200022 
 9.90       .10        .62        335.       13.                  4070100200023 
ENDDATA              9          0                                 4070100200024 
ENDSUBENT           23          0                                 4070100299999 
ENDENTRY             2          0                                 4070199999999