ENTRY 30111 20240215 32133011100000001 SUBENT 30111001 20240215 32133011100100001 BIB 15 26 3011100100002 TITLE Investigation of delayed neutrons arising from the 3011100100003 fission of U238 nuclei by 14.7-MeV neutrons 3011100100004 AUTHOR (M.Buczko) 3011100100005 INSTITUTE (3HUNDEB) 3011100100006 REFERENCE (J,SJA,20,187,1966) 3011100100007 (J,AE,20,153,1966) Russ. orig. of SJA 20 3011100100008 (J,JNE,21,302,1967) English translation of AE 20 3011100100009 (J,EAF,20,(2),81,1966) French translation of AE 20 3011100100010 FACILITY (NGEN,3HUNDEB) Atomki 300-keV neutron generator 3011100100011 INC-SOURCE (D-D,D-T) 3011100100012 SAMPLE Natural U3O8 on polyethylene holder 3011100100013 METHOD (ACTIV) Measurements began 0.5 sec after a 30 min 3011100100014 irradiation 3011100100015 DETECTOR (BF3) for neutron flux determination 3011100100016 PART-DET (DN) 3011100100017 ANALYSIS (DECAY) Delayed neutron decay curve obtained analysed 3011100100018 by graphical iteration method 3011100100019 CORRECTION No correction given 3011100100020 ERR-ANALYS No error analysis given 3011100100021 STATUS (TABLE,,M.Butsko,J,JNE,21,302,1967) Table 1 3011100100022 (APRVD) Approved by Angeli (6/7/72) 3011100100023 HISTORY (19670830C) Compiled in DASTAR-218 3011100100024 (19720106T) CA. Converted to EXFOR. 3011100100025 (20050624A) OS. Reaction code in subentry 2 3011100100026 corrected. 3011100100027 (20240215U) On. TITLE updated. 3011100100028 ENDBIB 26 0 3011100100029 NOCOMMON 0 0 3011100100030 ENDSUBENT 29 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