ENTRY 40138 20150109 41724013800000001 SUBENT 40138001 20150109 41724013800100001 BIB 15 54 4013800100002 TITLE Energy dependence of average neutron number 4013800100003 for fast-neutron fission of U-238 4013800100004 AUTHOR (M.V.Sabin,Yu.A.Khokhlov,I.N.Paramonova,V.A.Chirkin) 4013800100005 M.V.Sabin= M.V.Savin 4013800100006 INSTITUTE (4RUSKUR) 4013800100007 REFERENCE (J,SJA,32,474,1972) Eng.Trans.of AE,32,408,1972 4013800100008 (J,AE,32,408,197205) 4013800100009 (R,FEI-12,16,1971) abstract, data given 4013800100010 ((C,71KIEV,1,328,1971)=(R,INDC(CCP)-456,328,1972)) 4013800100011 Prelim.publication. 4013800100012 MONITOR ((MONIT)98-CF-252(0,F),PR,NU) Cf-252 layer was used to 4013800100013 measure gamma and neutron detection efficiency to be 4013800100014 0.347+-0.002 and 0.700+-0.003, respectively. 4013800100015 FACILITY (LINAC,4RUSKUR) Electron linear accelerator 4013800100016 METHOD (TOF) The time-of-flight method (resolution 1 nsec/m) 4013800100017 Flight path 35 m. 4013800100018 SAMPLE The U-238 sample consisted of a stack of metal discs 4013800100019 15 mm in diameter and 1 mm thick with a total 4013800100020 mass of 20 g. 4013800100021 DETECTOR (STANK) The liquid scintillation detector, ~400 litre 4013800100022 PART-DET (G,N) Fission gamma and neutron. 4013800100023 CORRECTION For background of scattered neutrons ( measured with 4013800100024 lead sample) - 4-8% . 4013800100025 ERR-ANALYS (ERR-T) The indicated errors are mean square. Following4013800100026 errors the following were taken into account: 4013800100027 (ERR-S,1.5,2.) The statistical accuracy of each set 4013800100028 is 1.5 - 2%. 4013800100029 (ERR-1) variation of the neutron counting efficiency 4013800100030 as a result of the instability of the apparatus ; 4013800100031 (ERR-2) the error due to the inaccuracy in determining 4013800100032 background; 4013800100033 (ERR-3) the error arising in the determination of the 4013800100034 number of cases of radiative capture of neutrons. 4013800100035 COMMENT In the region of neutron energy below 3 MeV the NU(En)4013800100036 dependence is described by a straight line with 4013800100037 the slope dNU/dEn=0.10 and in the region above 3 MeV 4013800100038 -by straight line with the slope dNU/dEn=0.18 4013800100039 STATUS (TABLE) Table 1 of SJA,32,474 4013800100040 = Table of 71KIEV,1,328,1971 4013800100041 HISTORY (19730310C) 4013800100042 (19740920U) 4013800100043 (19870612U) Several obsolete keywords corrected, one 4013800100044 Reference introduced (AE,32,408,72), ISO-QUANT 4013800100045 into REACTION converted 4013800100046 (20150109A) SD: Updated to new date formats,lower case.4013800100047 Ref. on Engl.transl. of AE added. Author's name 4013800100048 corrected. BIB updated (ERR-ANALYS added). DATA units4013800100049 in Subent 002 changed (NO-DIM -> PRT/FIS). 4013800100050 Ref. on 71KIEV added. 4013800100051 (20151020A) M.M. Articles were checked, BIB information4013800100052 was updated in AUTHOR, MONITOR, PART-DET,CORRECTION, 4013800100053 ANALYSIS. 4013800100054 MONIT was added in COMMON. REACTION was corrected. 4013800100055 DATA-ERR -> ERR-T . 4013800100056 ENDBIB 54 0 4013800100057 COMMON 4 3 4013800100058 ERR-1 ERR-2 ERR-3 MONIT 4013800100059 PER-CENT PER-CENT PER-CENT PRT/FIS 4013800100060 0.5 1. 0.5 3.756 4013800100061 ENDCOMMON 3 0 4013800100062 ENDSUBENT 61 0 4013800199999 SUBENT 40138002 20150109 41724013800200001 BIB 3 14 4013800200002 REACTION (92-U-238(N,F),PR,NU) 4013800200003 The values of NU are averaged over two sets of 4013800200004 measurements performed at different times. 4013800200005 ANALYSIS In calculating of NU, the following were taken into 4013800200006 account: 4013800200007 - angular correlation of fission neutrons and incident 4013800200008 neutrons arising as a consequence of fragments angular 4013800200009 anisotropy; 4013800200010 - the variation of mean energy of fission neutrons with4013800200011 increasing NU and the difference between Cf-252 4013800200012 fission-neutron spectrum ( used for calibration) and 4013800200013 U-238 fission-neutron spectrum; 4013800200014 - the neutron multiplication in the sample. 4013800200015 HISTORY (20151020A) M.M. PR was added in SF5 . 4013800200016 ENDBIB 14 0 4013800200017 NOCOMMON 0 0 4013800200018 DATA 3 46 4013800200019 EN DATA ERR-T 4013800200020 MEV PRT/FIS PRT/FIS 4013800200021 1.27 2.503 0.055 4013800200022 1.30 2.498 0.052 4013800200023 1.33 2.544 0.051 4013800200024 1.35 2.575 0.049 4013800200025 1.42 2.591 0.046 4013800200026 1.45 2.591 0.046 4013800200027 1.48 2.518 0.045 4013800200028 1.51 2.470 0.044 4013800200029 1.55 2.467 0.042 4013800200030 1.58 2.576 0.044 4013800200031 1.62 2.577 0.041 4013800200032 1.70 2.639 0.042 4013800200033 1.78 2.552 0.041 4013800200034 1.82 2.589 0.041 4013800200035 1.87 2.586 0.041 4013800200036 1.92 2.543 0.041 4013800200037 1.97 2.621 0.039 4013800200038 2.02 2.591 0.039 4013800200039 2.07 2.587 0.041 4013800200040 2.13 2.612 0.039 4013800200041 2.18 2.610 0.039 4013800200042 2.24 2.618 0.042 4013800200043 2.31 2.653 0.042 4013800200044 2.37 2.679 0.043 4013800200045 2.44 2.708 0.043 4013800200046 2.51 2.652 0.042 4013800200047 2.59 2.609 0.044 4013800200048 2.66 2.630 0.045 4013800200049 2.74 2.613 0.044 4013800200050 2.83 2.661 0.045 4013800200051 2.92 2.644 0.047 4013800200052 3.11 2.689 0.048 4013800200053 3.21 2.721 0.049 4013800200054 3.32 2.721 0.049 4013800200055 3.43 2.812 0.053 4013800200056 3.55 2.778 0.053 4013800200057 3.68 2.819 0.056 4013800200058 3.80 2.680 0.057 4013800200059 3.94 2.886 0.058 4013800200060 4.09 2.911 0.061 4013800200061 4.24 2.876 0.058 4013800200062 4.50 2.981 0.057 4013800200063 4.86 3.023 0.057 4013800200064 5.39 3.095 0.080 4013800200065 5.62 3.186 0.092 4013800200066 5.87 3.184 0.092 4013800200067 ENDDATA 48 0 4013800200068 ENDSUBENT 67 0 4013800299999 ENDENTRY 2 0 4013899999999