ENTRY 30561 20150407 31693056100000001 SUBENT 30561001 20150407 31693056100100001 BIB 19 114 3056100100002 TITLE Measurement of cross sections for the U-238(n,2n) 3056100100003 reaction from 6.5 to 14.8 MeV 3056100100004 AUTHOR (N.V.Kornilov, B.V.Zhuravlev, O.A.Sal'nikov, P.Raics, 3056100100005 S.Nagy, S.Daroczy, K.Sailer, J.Csikai) 3056100100006 INSTITUTE (4RUSFEI,3HUNKOS) 3056100100007 REFERENCE (S,ZFK-410,68,1980) 3056100100008 Experiment described and table up to 10.5 MeV 3056100100009 (P,INDC(HUN)-17,47,1980) Abstract, table 6.5 - 14.8 MeV3056100100010 (J,AE,49,283,1980) table up to 10.5 MeV 3056100100011 (J,SJA,49,722,1980) English translation of AE 3056100100012 #doi:10.1007/BF01120739 3056100100013 (C,80KIEV,1,236,1980) See COMMENT 3056100100014 (R,INDC(CCP)-154,1980) (002 data tabulated Table 4 of 3056100100015 this report, same as ZFK-410) 3056100100016 SAMPLE Oxide samples in form of disc (18.5 mm in diameter, 3056100100017 1.-1.7 mm thick, 1.9-2.8 g) more than 99.99% U-238. 3056100100018 Chemical composition 90.0+-.6% uranium 3056100100019 MONITOR 1(92-U-238(N,F),,SIG) 3056100100020 2(13-AL-27(N,A)11-NA-24,,SIG) 3056100100021 3(26-FE-56(N,P)25-MN-56,,SIG) 3056100100022 COMMENT ===Compiler's note=== 3056100100023 For the energy range 6.5 to 10.5 MeV, authors give 3056100100024 different representation of results in the Proceedings3056100100025 of the 1980 Kiev Conference (vol.1,p.236). 3056100100026 The 4 cross-sections 238U(n,2n), 238U(n,f), 27Al(n,a) 3056100100027 and 56Fe(n,p) are given relative to one another. 3056100100028 See EXFOR 30590. 3056100100029 MONIT-REF 1(,M.G.Sowerby+,J,ANE,1,409,197407) 3056100100030 2(,Y.Kanda+,C,68WASH,1,193,196809) 3056100100031 3(,Y.Kanda+,C,68WASH,1,193,196809) 3056100100032 FACILITY (VDGT,4RUSFEI) 10 MeV maximum deuteron energy 3056100100033 (CCW,3HUNKOS) 13.5-14.8 MeV 3056100100034 INC-SOURCE (D-D) 40 mm long gas target. 3056100100035 106.6 kPa except the cases 6.54 and 6.78 MeV neutrons,3056100100036 when p=66.6 kPa 3056100100037 (D-T) 13.5-14.8 MeV neutrons 3056100100038 METHOD (ACTIV) Uranium samples between Al and Fe foils were 3056100100039 put on a fission chamber (for neutron flux 3056100100040 measurements by 238U(n,f)) and placed on the beam line3056100100041 40+/-5 mm from the end of the gas target. 3056100100042 DETECTOR (GELI) Germanium-lithium detector for gamma-activity 3056100100043 measurement of 24Na, 56Mn, 237U and standard sources 3056100100044 INC-SPECT The average value and dispersion of the energy of the 3056100100045 incident neutrons were calculated from the deuteron 3056100100046 stopping and reaction kinematics using data from 3056100100047 H.Liskien+ (1973) and C.W.Williamson+ (1966). 3056100100048 REL-REF (R,,H.Liskien+,J,ND/A,11,569,1973) 3056100100049 (R,,C.W.Williamson+,R,CEA-R-3042,1966) 3056100100050 CORRECTION The following corrections were taken into account 3056100100051 A. In flux determination for fiss. detector 3056100100052 Losses in pulses due to the discrimination 3056100100053 Threshold 3056100100054 Self-absorption in the layer 3056100100055 Laboratory angular distribution of fragments 3056100100056 all not exceed 2.5 +- 1.% 3056100100057 Effect of D(d,np)D neutrons on the fission counts 3056100100058 was 1.0+-.5% for En=8.5 MeV and 18.+-.4 for 3056100100059 En=10.5 MeV. 3056100100060 Corrections for (d,n) neutrons from the struct. 3056100100061 materials were determined by experiments and 3056100100062 were 1.0+-.5% for En=6.54 MeV and 11.+-1.% 3056100100063 for En=10.50 MeV. 3056100100064 The accuracy of flux determination by fission 3056100100065 chamber was evaluated from 1.to 4.% without 3056100100066 the uncertainty in the (n,f) cross-section 3056100100067 B. In flux determination by activation method 3056100100068 Background effects of (d,n) neutrons 3056100100069 Decrease in the neutron flux density along the 3056100100070 sample thickness 3056100100071 Flux variation in time 3056100100072 The accuracy of flux determination by activation 3056100100073 method was not better than 1.% for En=6.54 3056100100074 MeV and 3.% for En=10.5 MeV without the uncertainty3056100100075 in the (n,a) and (n,p) cross-sections. 3056100100076 DECAY-DATA (92-U-237,6.75D,DG,208.0,0.2180) 3056100100077 ERR-ANALYS (EN-ERR) See explanation under INC-SPECT 3056100100078 (ERR-T) Total error 3056100100079 (ERR-S,,3.) Statistical error was less than 1% for all 3056100100080 energies except for En=6.54 MeV (3%) and En=6.78 MeV 3056100100081 (2%). 3056100100082 (ERR-1) Standard error of the mean for the averaged 3056100100083 flux density as well as error of the determination 3056100100084 of the U-238 mass. 3056100100085 The average flux density was calculated as 3056100100086 F=(F(n,a)+F(n,p)+K*F(n,f))/(2+K), 3056100100087 where the values of average flux, error in 3056100100088 determination of average flux and K are given below: 3056100100089 Inc.En Av.flux dens.(AFD) Err.in AFD K 3056100100090 (MeV) (*10**6/cm2/sec) (*10**6/cm2/sec) 3056100100091 6.54 2.19 0.13 2 3056100100092 6.78 1.76 0.08 2 3056100100093 7.00 3.49 0.12 2 3056100100094 7.50 3.48 0.09 1 3056100100095 7.50 3.92 0.12 1 3056100100096 7.99 3.68 0.06 1 3056100100097 8.50 3.94 0.08 1 3056100100098 8.99 4.20 0.04 1 3056100100099 8.99 4.53 0.09 1 3056100100100 9.49 2.72 0.03 0.5 3056100100101 10.00 4.08 0.04 0.5 3056100100102 10.50 4.38 0.15 0.5 3056100100103 (ERR-2) GeLi-detector efficiency 3056100100104 (ERR-3) Self-absorption correction 3056100100105 (ERR-4) Branching intensity of the 208. keV line 3056100100106 STATUS (TABLE) Data were taken from Table 1,ZFK-410,p.70 and 3056100100107 INDC(HUN)-17,47 Table 1. 3056100100108 (APRVD) P.Raics- 1986/10/28 3056100100109 HISTORY (19810108C) VP. 3056100100110 (19811027A) OS.-Num.values added to subentry 2, 3056100100111 refs.+comment added, further BIB changes in subent.1. 3056100100112 (19881012A) VOF-Reference added+author's approval 3056100100113 (20090503A) SD:Updated to new date formats,lower case. 3056100100114 (20120225U) On. REFERENCE: doi identifier corrected 3056100100115 (20150402U) VS. R,INDC(CCP)-154, 1980 added. 3056100100116 ENDBIB 114 0 3056100100117 NOCOMMON 0 0 3056100100118 ENDSUBENT 117 0 3056100199999 SUBENT 30561002 20090505 31373056100200001 BIB 2 3 3056100200002 REACTION (92-U-238(N,2N)92-U-237,,SIG) 3056100200003 COMMENT === Compiler's note 81/02/02 3056100200004 Two measurements were done for En=7.5 and 8.99=MeV 3056100200005 ENDBIB 3 0 3056100200006 NOCOMMON 0 0 3056100200007 DATA 9 17 3056100200008 EN +EN-ERR -EN-ERR DATA ERR-1 ERR-2 3056100200009 ERR-3 ERR-4 ERR-T 3056100200010 MEV MEV MEV MB PER-CENT PER-CENT 3056100200011 PER-CENT PER-CENT MB 3056100200012 6.5400E+00 9.0000E-02 7.0000E-02 7.2000E+01 6.0000E-01 2.0000E+003056100200013 1.5000E+00 1.0000E+00 5.0000E+00 3056100200014 6.7800E+00 8.0000E-02 6.0000E-02 2.5100E+02 6.0000E-01 2.0000E+003056100200015 1.5000E+00 1.0000E+00 1.3000E+01 3056100200016 7.0000E+00 1.0000E-01 7.0000E-02 4.0200E+02 6.0000E-01 2.0000E+003056100200017 1.5000E+00 1.0000E+00 1.8000E+01 3056100200018 7.5000E+00 1.0000E-01 7.0000E-02 8.3000E+02 6.0000E-01 2.0000E+003056100200019 1.5000E+00 1.0000E+00 3.0000E+01 3056100200020 7.5000E+00 1.0000E-01 7.0000E-02 8.3200E+02 6.0000E-01 2.0000E+003056100200021 1.5000E+00 1.0000E+00 3.2000E+01 3056100200022 7.9900E+00 1.0000E-01 8.0000E-02 1.0770E+03 6.0000E-01 2.0000E+003056100200023 1.5000E+00 1.0000E+00 3.1000E+01 3056100200024 8.5000E+00 1.0000E-01 8.0000E-02 1.2440E+03 6.0000E-01 2.0000E+003056100200025 1.5000E+00 1.0000E+00 4.1000E+01 3056100200026 8.9900E+00 1.0000E-01 8.0000E-02 1.3450E+03 6.0000E-01 2.0000E+003056100200027 1.5000E+00 1.0000E+00 3.5000E+01 3056100200028 8.9900E+00 1.0000E-01 8.0000E-02 1.3430E+03 6.0000E-01 2.0000E+003056100200029 1.5000E+00 1.0000E+00 4.2000E+01 3056100200030 9.4900E+00 8.0000E-02 8.0000E-02 1.3710E+03 6.0000E-01 2.0000E+003056100200031 1.5000E+00 1.0000E+00 3.6000E+01 3056100200032 1.0000E+01 8.0000E-02 8.0000E-02 1.4130E+03 6.0000E-01 2.0000E+003056100200033 1.5000E+00 1.0000E+00 3.7000E+01 3056100200034 1.0490E+01 8.0000E-02 8.0000E-02 1.4660E+03 6.0000E-01 2.0000E+003056100200035 1.5000E+00 1.0000E+00 6.3000E+01 3056100200036 1.3540E+01 1.1000E-01 1.1000E-01 1.0660E+03 3056100200037 4.8000E+01 3056100200038 1.3760E+01 1.0000E-01 1.0000E-01 9.9700E+02 3056100200039 4.5000E+01 3056100200040 1.4100E+01 1.0000E-01 1.2000E-01 8.7300E+02 3056100200041 4.0000E+01 3056100200042 1.4420E+01 1.1000E-01 1.1000E-01 7.8000E+02 3056100200043 3.5000E+01 3056100200044 1.4760E+01 1.4000E-01 1.7000E-01 6.7800E+02 3056100200045 3.0000E+01 3056100200046 ENDDATA 38 0 3056100200047 ENDSUBENT 46 0 3056100299999 ENDENTRY 2 0 3056199999999