ENTRY 40262 20070426 41404026200000001 SUBENT 40262001 20070426 41404026200100001 BIB 11 36 4026200100002 INSTITUTE (4RUSKUR) 4026200100003 REFERENCE (J,YF,16,(6),1161,197212) Graphs Are Given 4026200100004 (C,75KIEV,5,186,197506) Data Table given. 4026200100005 (J,SNP,16,(6),638,197306) 4026200100006 AUTHOR (M.V.SAVIN,JU.A.KHOHLOV,A.E.SAVELJEV,I.N.PARAMONOVA) 4026200100007 TITLE ENERGY DEPENDENCE NU-BAR IN U-235 FISSION 4026200100008 WITH FAST NEUTRONS 4026200100009 FACILITY (LINAC) Electron Linear Accelerator 4026200100010 METHOD (TOF) Time-of-flight path 35 m. 4026200100011 DETECTOR (SCIN) Liquid Scintillation Detector of 400L volume.4026200100012 (IOCH) Ionization chamber with Cf-252 layer for 4026200100013 mesurement of gamma-rays registration efficiency. 4026200100014 Gamma quanta registration efficiency 0.347+-0.002 . 4026200100015 Fission neutron registration efficiency 0.700+-0.004. 4026200100016 STATUS (COREL,40523001) Data Obtained From Author. 4026200100017 See also Table 2 of 2nd Reference. 4026200100018 HISTORY (19750107C) Compiled At The Centre 4026200100019 (20060814U) M.M. BIB information was added. 4026200100020 Dates were corrected for 4-digits year. 4026200100021 (20070426U) COMMON and BIB informatio were added. M.M 4026200100022 CORRECTION At Nu-bar Calculation 4026200100023 1) Incident Neutron-fission Angle Correlation 4026200100024 2) Average Energy Change Of Fission Neutron With Nu-bar4026200100025 Increase And Difference Of Fission Neutron Spectrum Of 4026200100026 Cf-252 From One Of Isotope Studied 4026200100027 3)Multiplication Of Neutron Formed Into Sample Studied 4026200100028 Were Taken Into Account 4026200100029 ERR-ANALYS (DATA-ERR) At Calculation Of Errors 4026200100030 1)Statistical Calculation 4026200100031 (ERR-1) 2)Change Of Neutron Registration Efficiency 4026200100032 Because Of Instability Of Apparatus 4026200100033 (ERR-2) 3)Error Of Background Measurement By Means Of 4026200100034 Lead Sample 4026200100035 (ERR-3) 4)Error Of Correction On Starting Of Time 4026200100036 Channel at En < 0.9 MeV By Fission Neutron 4026200100037 Were Taken Into Account 4026200100038 ENDBIB 36 0 4026200100039 COMMON 3 3 4026200100040 ERR-1 ERR-2 ERR-3 4026200100041 PER-CENT PER-CENT PER-CENT 4026200100042 0.5 1. 0.5 4026200100043 ENDCOMMON 3 0 4026200100044 ENDSUBENT 43 0 4026200199999 SUBENT 40262002 19850329 41404026200200001 BIB 3 3 4026200200002 REACTION (92-U-235(N,F),PR,NU) 4026200200003 MONITOR ((MONIT)98-CF-252(0,F),PR,NU) 4026200200004 SAMPLE Metallic Uranium discs of 17.4 g weight(90% enrichment)4026200200005 ENDBIB 3 0 4026200200006 COMMON 1 3 4026200200007 MONIT 4026200200008 NO-DIM 4026200200009 3.7560E+00 4026200200010 ENDCOMMON 3 0 4026200200011 DATA 3 30 4026200200012 EN DATA DATA-ERR 4026200200013 MEV PRT/FIS PRT/FIS 4026200200014 8.6000E-01 2.4720E+00 4.0000E-02 4026200200015 9.0000E-01 2.5170E+00 4.0000E-02 4026200200016 9.5000E-01 2.4810E+00 4.0000E-02 4026200200017 9.9000E-01 2.4770E+00 4.0000E-02 4026200200018 1.0300E+00 2.4810E+00 4.0000E-02 4026200200019 1.0900E+00 2.5390E+00 4.0000E-02 4026200200020 1.1600E+00 2.5490E+00 4.0000E-02 4026200200021 1.2300E+00 2.5590E+00 3.8000E-02 4026200200022 1.2900E+00 2.5980E+00 3.8000E-02 4026200200023 1.3600E+00 2.6200E+00 4.0000E-02 4026200200024 1.4500E+00 2.6260E+00 3.8000E-02 4026200200025 1.5400E+00 2.6020E+00 4.0000E-02 4026200200026 1.6300E+00 2.6170E+00 4.0000E-02 4026200200027 1.7300E+00 2.6370E+00 4.0000E-02 4026200200028 1.8100E+00 2.6310E+00 4.0000E-02 4026200200029 1.9000E+00 2.6520E+00 4.0000E-02 4026200200030 2.0500E+00 2.6590E+00 3.8000E-02 4026200200031 2.2400E+00 2.6830E+00 3.5000E-02 4026200200032 2.4200E+00 2.7160E+00 3.5000E-02 4026200200033 2.5900E+00 2.7590E+00 3.5000E-02 4026200200034 2.7800E+00 2.8130E+00 3.5000E-02 4026200200035 3.0000E+00 2.8170E+00 3.5000E-02 4026200200036 3.2500E+00 2.8510E+00 4.0000E-02 4026200200037 3.4800E+00 2.8540E+00 4.5000E-02 4026200200038 3.7300E+00 2.8970E+00 4.5000E-02 4026200200039 4.1300E+00 2.9160E+00 5.0000E-02 4026200200040 4.4000E+00 2.9840E+00 6.0000E-02 4026200200041 4.6800E+00 3.0210E+00 6.5000E-02 4026200200042 4.9900E+00 3.0990E+00 6.5000E-02 4026200200043 5.3500E+00 3.1700E+00 8.0000E-02 4026200200044 ENDDATA 32 0 4026200200045 ENDSUBENT 44 0 4026200299999 ENDENTRY 2 0 4026299999999