ENTRY 12419 20180521 14411241900000001 SUBENT 12419001 20180521 14411241900100001 BIB 8 27 1241900100002 TITLE Energy Dependence of Prompt nu bar for 1241900100003 Neutron-Induced Fission of U235 1241900100004 AUTHOR (J.W.Meadows,J.F.Whalen) 1241900100005 REFERENCE (J,PR,126,197,1962) 1241900100006 #doi:10.1103/PhysRev.126.197 1241900100007 INSTITUTE (1USAANL) 1241900100008 FACILITY (VDG,1USAANL) electrostatic accelerator. 1241900100009 INC-SOURCE (P-LI7) Beam of neutrons from a Li7(p,n)Be7 source. 1241900100010 METHOD (FISCT,COINC) The method used involved the 1241900100011 measurement of coincidences between a fission counter 1241900100012 and a neutron detector. In order to avoid the 1241900100013 possibility of a change in the accidental rate or in 1241900100014 the efficiency of the neutron detector, measurements 1241900100015 of U235, Cf252 and the accidentals were made 1241900100016 simultaneously. Two fission pulse ionization chambers 1241900100017 were placed in a common container. In each of the 1241900100018 chambers the fissionable material was spread over 1241900100019 nine foils having a diameter of 6.5 cm. The U235 1241900100020 chamber contained ~80 mg of material while the Cf252 1241900100021 chamber contained enough material to give ~300 1241900100022 fissions per minute. The two chambers were separated 1241900100023 by a bare foil and 2 cm of the counter gas. 1241900100024 HISTORY (19760804T) Translated from SCISRS. 1241900100025 (19820519A) Converted to reaction formalism 1241900100026 (20180521A) BP: Updated to new date formats, lower 1241900100027 case, doi, experiment description, separated 252Cf 1241900100028 into a separate measurement. Sub.5 added. 1241900100029 ENDBIB 27 0 1241900100030 NOCOMMON 0 0 1241900100031 ENDSUBENT 30 0 1241900199999 SUBENT 12419002 20180521 14411241900200001 BIB 4 11 1241900200002 REACTION 1((92-U-235(N,F),PR,NU)/ 1241900200003 (98-CF-252(0,F),PR,NU)) 1241900200004 2(92-U-235(N,F),PR,NU) 1241900200005 ERR-ANALYS2(ERR-1) Relative error, no details on sources. 1241900200006 (ERR-T) Total error, no details on sources. 1241900200007 CORRECTION A series of six corrections for the U235/Cf252 ratio: 1241900200008 second neutron group, thermal neutron induced fission, 1241900200009 analyzer dead time, asymmetry of the neutron detector, 1241900200010 energy dependence of the neutron detector, fission 1241900200011 fragment angular distributions. 1241900200012 STATUS (TABLE) Table I, page 199. 1241900200013 ENDBIB 11 0 1241900200014 NOCOMMON 0 0 1241900200015 DATA 5 6 1241900200016 EN DATA 1DATA 2ERR-1 2ERR-T 2 1241900200017 MEV NO-DIM PRT/FIS PER-CENT PER-CENT 1241900200018 0.03 0.6449 2.421 1.04 1.61 1241900200019 0.20 0.6491 2.436 0.66 1.40 1241900200020 0.62 0.6580 2.470 0.78 1.46 1241900200021 1.11 0.6713 2.520 0.72 1.42 1241900200022 1.58 0.6870 2.580 0.76 1.45 1241900200023 1.76 0.6860 2.575 0.80 1.47 1241900200024 ENDDATA 8 0 1241900200025 ENDSUBENT 24 0 1241900299999 SUBENT 12419003 19820519 00001241900300001 BIB 3 3 1241900300002 REACTION (92-U-235(N,F),PR,NU) 1241900300003 STATUS SEE 12419,2 FOR DATA 1241900300004 HISTORY (800507A) DATA DELETED 1241900300005 ENDBIB 3 0 1241900300006 NOCOMMON 0 0 1241900300007 NODATA 0 0 1241900300008 ENDSUBENT 7 0 1241900399999 SUBENT 12419004 19820519 00001241900400001 BIB 5 7 1241900400002 REACTION (92-U-235(N,F),PR,NU) 1241900400003 STATUS (SPSDD) 1241900400004 REFERENCE (C,61VIENNA,,125,6108) 1241900400005 DETECTOR (PROPC) ROW OF BF3 COUNTERS EMBEDDED IN POLYETHYLENE. 1241900400006 MONITOR (92-U-235(N,F),PR,NU) 1241900400007 RELATIVE TO U-235 THERMAL NU(PROMPT) 1241900400008 =2.42. 1241900400009 ENDBIB 7 0 1241900400010 NOCOMMON 0 0 1241900400011 NODATA 0 0 1241900400012 ENDSUBENT 11 0 1241900499999 SUBENT 12419005 20180521 14411241900500001 BIB 4 4 1241900500002 REACTION (98-CF-252(0,F),PR,NU) 1241900500003 ERR-ANALYS (DATA-ERR) No details on sources. 1241900500004 STATUS (TABLE) Table I, page 199. 1241900500005 HISTORY (20180521C) BP 1241900500006 ENDBIB 4 0 1241900500007 NOCOMMON 0 0 1241900500008 DATA 2 1 1241900500009 DATA DATA-ERR 1241900500010 PRT/FIS PER-CENT 1241900500011 3.754 1.27 1241900500012 ENDDATA 3 0 1241900500013 ENDSUBENT 12 0 1241900599999 ENDENTRY 5 0 1241999999999