ENTRY 30111 20050624 31173011100000001 SUBENT 30111001 20050624 31173011100100001 BIB 14 27 3011100100002 INSTITUTE (3HUNDEB) 3011100100003 REFERENCE (J,AE,20,(2),153,196602) 3011100100004 (J,EAF,20,(2),81,196602)French translation of AE 20 3011100100005 (J,SJA,20,187,196602)English translation of AE 20 3011100100006 (J,JNE,21,302,1967)English translation of AE 20 3011100100007 AUTHOR (M.BUCZKO) 3011100100008 TITLE Delayed neutrons emitted in the 14.7MeV neutron-induced3011100100009 fission of U-238 3011100100010 INC-SOURCE (D-D) D(d,n)He-3 reaction 3011100100011 (D-T) T(d,n)alpha reaction 3011100100012 Neutron flux determined by BF3 counter 3011100100013 SAMPLE Oxide- U3-O8 of natural composition on polyethylene 3011100100014 holder 3011100100015 METHOD (ACTIV) The measurements began 0.5 sec after a 30 min 3011100100016 irradiation. Activation-measurement. 3011100100017 DETECTOR (BF3,LONGC) BF3 long counter. 3011100100018 PART-DET (DN)Delayed neutrons 3011100100019 ANALYSIS The delayed neutron decay curve obtained was analysed 3011100100020 by the graphical iteration method 3011100100021 CORRECTION No correction given 3011100100022 ERR-ANALYS No error analysis given 3011100100023 STATUS Data taken from table in Atomnaya Energiya 20,153 3011100100024 (APRVD) Approved by Angeli (6/7/72) 3011100100025 HISTORY (19670830C) Compiled in DASTAR-218 3011100100026 (19720106T) CA. Converted to EXFOR 3011100100027 (20050624A) OS. Reaction code in subentry 2 3011100100028 corrected. Changed to 4-dig.year and lower case 3011100100029 ENDBIB 27 0 3011100100030 NOCOMMON 0 0 3011100100031 ENDSUBENT 30 0 3011100199999 SUBENT 30111002 20050624 31173011100200001 BIB 1 4 3011100200002 REACTION ((92-U-238(N,F),DL/GRP,NU)// 3011100200003 (92-U-238(N,F),DL/GRP,NU)) 3011100200004 The yields of delayed neutrons emitted in the U-238 3011100200005 fission are normalised to the second group of neutrons 3011100200006 ENDBIB 4 0 3011100200007 COMMON 2 3 3011100200008 EN HL-DN 3011100200009 MEV SEC 3011100200010 1.4700E+01 2.000E+01 3011100200011 ENDCOMMON 3 0 3011100200012 DATA 2 4 3011100200013 HL-NM DATA 3011100200014 SEC NO-DIM 3011100200015 5.6000E+01 1.4500E-01 3011100200016 4.6000E+00 1.0870E+00 3011100200017 1.8000E+00 2.4170E+00 3011100200018 6.0000E-01 1.4500E+00 3011100200019 ENDDATA 6 0 3011100200020 ENDSUBENT 19 0 3011100299999 SUBENT 30111003 20050624 31173011100300001 BIB 1 3 3011100300002 REACTION ((92-U-238(N,F),DL,NU)//(92-U-238(N,F),DL,NU)) 3011100300003 Ratio of the total yield of delayed neutrons at 14.7 3011100300004 MeV by the total yield of delayed neutrons at 3 MeV 3011100300005 ENDBIB 3 0 3011100300006 COMMON 2 3 3011100300007 EN-NM EN-DN 3011100300008 MEV MEV 3011100300009 1.4700E+01 3.0000E+00 3011100300010 ENDCOMMON 3 0 3011100300011 DATA 2 1 3011100300012 DATA DATA-ERR 3011100300013 NO-DIM PER-CENT 3011100300014 1.6000E+00 1.0000E+01 3011100300015 ENDDATA 3 0 3011100300016 ENDSUBENT 15 0 3011100399999 ENDENTRY 3 0 3011199999999