ENTRY 30238 20081203 31323023800000001 SUBENT 30238001 20081203 31323023800100001 BIB 11 20 3023800100002 INSTITUTE (3ISLSOR) 3023800100003 REFERENCE (P,IA-1190,95,196907) 3023800100004 AUTHOR (A.Notea) 3023800100005 TITLE Delayed neutrons from thermal and 14 MeV neutron 3023800100006 fission of uranium and thorium 3023800100007 METHOD Number of fissions in the samples was determined from 3023800100008 the known gamma-ray peaks of the fission products, 3023800100009 measured with a Ge(Li) spectrometer. 3023800100010 DETECTOR (GELI) Flat response Ge(Li) detector 3023800100011 MONITOR (92-U-235(N,F),DL,NU) 3023800100012 Assumed delayed neutron yield for 3023800100013 U235 was 0.0151 neutrons/fission 3023800100014 CORRECTION Not given 3023800100015 ERR-ANALYS (DATA-ERR) Details not given 3023800100016 STATUS (TABLE) Data taken from IA-1190 95 7/1969 3023800100017 (APRVD) approved by Notea (1973/11/04) 3023800100018 HISTORY (19730526C) FM. 3023800100019 (20050624A) OS. Reaction code in subents 6,7 corrected.3023800100020 Changed to 4-dig.year and lower case 3023800100021 (20080211A) BIB section updated 3023800100022 ENDBIB 20 0 3023800100023 NOCOMMON 0 0 3023800100024 ENDSUBENT 23 0 3023800199999 SUBENT 30238002 20081203 31323023800200001 BIB 2 3 3023800200002 REACTION ((92-U-233(N,F),DL,NU)/ 3023800200003 (92-U-235(N,F),DL,NU)) 3023800200004 HISTORY (20080430S) Dataset was restored. 3023800200005 ENDBIB 3 0 3023800200006 NOCOMMON 0 0 3023800200007 DATA 3 1 3023800200008 EN DATA DATA-ERR 3023800200009 EV NO-DIM NO-DIM 3023800200010 0.0253 0.345 0.086 3023800200011 ENDDATA 3 0 3023800200012 ENDSUBENT 11 0 3023800299999 SUBENT 30238003 20081203 31323023800300001 BIB 2 3 3023800300002 REACTION ((94-PU-239(N,F),DL,NU)/ 3023800300003 (92-U-235(N,F),DL,NU)) 3023800300004 HISTORY (20080430S) Dataset was restored. 3023800300005 ENDBIB 3 0 3023800300006 NOCOMMON 0 0 3023800300007 DATA 3 1 3023800300008 EN DATA DATA-ERR 3023800300009 EV NO-DIM NO-DIM 3023800300010 0.0253 0.31 0.12 3023800300011 ENDDATA 3 0 3023800300012 ENDSUBENT 11 0 3023800399999 SUBENT 30238004 20081203 31323023800400001 BIB 2 3 3023800400002 REACTION ((92-U-238(N,F),DL,NU)/ 3023800400003 (92-U-235(N,F),DL,NU)) 3023800400004 HISTORY (20080430S) Dataset was restored. 3023800400005 ENDBIB 3 0 3023800400006 NOCOMMON 0 0 3023800400007 DATA 3 1 3023800400008 EN DATA DATA-ERR 3023800400009 MEV NO-DIM NO-DIM 3023800400010 14. 0.96 0.29 3023800400011 ENDDATA 3 0 3023800400012 ENDSUBENT 11 0 3023800499999 SUBENT 30238005 20081203 31323023800500001 BIB 2 3 3023800500002 REACTION ((90-TH-232(N,F),DL,NU)/ 3023800500003 (92-U-235(N,F),DL,NU)) 3023800500004 HISTORY (20080430S) Dataset was restored. 3023800500005 ENDBIB 3 0 3023800500006 NOCOMMON 0 0 3023800500007 DATA 3 1 3023800500008 EN DATA DATA-ERR 3023800500009 MEV NO-DIM NO-DIM 3023800500010 14. 0.77 0.30 3023800500011 ENDDATA 3 0 3023800500012 ENDSUBENT 11 0 3023800599999 SUBENT 30238006 20081203 31323023800600001 BIB 2 4 3023800600002 REACTION ((90-TH-232(N,F),DL/GRP,NU)/(90-TH-232(N,F),DL,NU)) 3023800600003 relative yields of five delayed 3023800600004 neutron groups in 14 MeV fission 3023800600005 HISTORY (20050624A) reaction corrected 3023800600006 ENDBIB 4 0 3023800600007 COMMON 1 3 3023800600008 EN 3023800600009 MEV 3023800600010 1.4000E+01 3023800600011 ENDCOMMON 3 0 3023800600012 DATA 3 5 3023800600013 GRP-NUM DATA DATA-ERR 3023800600014 NO-DIM NO-DIM NO-DIM 3023800600015 1.0000E+00 4.3600E-02 5.8000E-03 3023800600016 2.0000E+00 1.7700E-01 2.4000E-02 3023800600017 3.0000E+00 1.9600E-01 2.2000E-02 3023800600018 4.0000E+00 5.4400E-01 6.0000E-02 3023800600019 5.0000E+00 4.0000E-02 9.8000E-02 3023800600020 ENDDATA 7 0 3023800600021 ENDSUBENT 20 0 3023800699999 SUBENT 30238007 20081203 31323023800700001 BIB 2 5 3023800700002 REACTION ((92-U-238(N,F),DL/GRP,NU)/(92-U-238(N,F),DL,NU)) 3023800700003 Relative yields of five 3023800700004 delayed neutron groups in 14 MeV fission 3023800700005 HISTORY (19731114A) Iso-quant corrected 3023800700006 (20050624A) Reaction corrected 3023800700007 ENDBIB 5 0 3023800700008 COMMON 1 3 3023800700009 EN 3023800700010 MEV 3023800700011 1.4000E+01 3023800700012 ENDCOMMON 3 0 3023800700013 DATA 3 5 3023800700014 GRP-NUM DATA DATA-ERR 3023800700015 NO-DIM NO-DIM NO-DIM 3023800700016 1.0000E+00 2.2400E-02 3.1000E-03 3023800700017 2.0000E+00 1.6800E-01 2.2000E-02 3023800700018 3.0000E+00 2.0200E-01 1.8000E-02 3023800700019 4.0000E+00 4.1500E-01 3.7000E-02 3023800700020 5.0000E+00 1.9200E-01 8.7000E-02 3023800700021 ENDDATA 7 0 3023800700022 ENDSUBENT 21 0 3023800799999 ENDENTRY 7 0 3023899999999