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