ENTRY 12316 19860512 00001231600000001 SUBENT 12316001 19860512 00001231600100001 BIB 7 11 1231600100002 INSTITUTE (1USALAS) 1231600100003 REFERENCE (J,BAP,2,196(K4),5704) 1231600100004 AUTHOR (R.K.SMITH,R.L.HENKEL,R.A.NOBLES) 1231600100005 TITLE NEUTRON-INDUCED FISSION CROSS SECTIONS FOR U233, U235, 1231600100006 U238 AND PU241 FROM 2 TO 10 MEV. 1231600100007 INC-SOURCE (P-T) 1231600100008 (D-D) 1231600100009 STATUS (SCSRS) 1231600100010 HISTORY (760804T) TRANSLATED FROM SCISRS 1231600100011 (800512U)CONVERTED TO REACTION FORMALISM BIB CORRECTION1231600100012 (860512A) BIB UPDATE. 1231600100013 ENDBIB 11 0 1231600100014 NOCOMMON 0 0 1231600100015 ENDSUBENT 14 0 1231600199999 SUBENT 12316002 19860512 00001231600200001 BIB 4 4 1231600200002 REACTION (92-U-233(N,F),,SIG) 1231600200003 DETECTOR (FISCH) DOUBLE IONIZATION CHAMBER 1231600200004 MONITOR (92-U-238(N,F),,SIG) 1231600200005 STATUS (CURVE) READ FROM GRAPH. 1231600200006 ENDBIB 4 0 1231600200007 NOCOMMON 0 0 1231600200008 DATA 2 19 1231600200009 EN DATA 1231600200010 MEV B 1231600200011 2.0 +00 1.98 +00 1231600200012 2.5 +00 1.99 +00 1231600200013 3.0 +00 1.81 +00 1231600200014 3.5 +00 1.81 +00 1231600200015 4.0 +00 1.65 +00 1231600200016 4.5 +00 1.62 +00 1231600200017 5.0 +00 1.57 +00 1231600200018 5.5 +00 1.53 +00 1231600200019 6.0 +00 1.71 +00 1231600200020 6.25 +00 1.78 +00 1231600200021 6.5 +00 1.93 +00 1231600200022 6.75 +00 2.0 +00 1231600200023 7.0 +00 2.10 +00 1231600200024 7.5 +00 2.20 +00 1231600200025 8.0 +00 2.19 +00 1231600200026 8.5 +00 2.29 +00 1231600200027 9.0 +00 2.22 +00 1231600200028 9.5 +00 2.21 +00 1231600200029 1.0 +01 2.22 +00 1231600200030 ENDDATA 21 0 1231600200031 ENDSUBENT 30 0 1231600299999 SUBENT 12316003 19841018 00001231600300001 BIB 6 6 1231600300002 REACTION (92-U-235(N,F),,SIG) 1231600300003 STATUS (SPSDD,12316010) 1231600300004 REFERENCE (W,SMITH,6102) TABULATED DATA 1231600300005 DETECTOR (TELES) NEUTRON TELESCOPE 1231600300006 MONITOR (1-H-1(N,EL)1-H-1,,SIG) 1231600300007 HISTORY (841018U) BIB CORRECTION. 1231600300008 ENDBIB 6 0 1231600300009 NOCOMMON 0 0 1231600300010 NODATA 0 0 1231600300011 ENDSUBENT 10 0 1231600399999 SUBENT 12316004 19800528 00001231600400001 BIB 6 6 1231600400002 REACTION (92-U-235(N,F),,SIG) 1231600400003 REFERENCE (W,SMITH,6809) 1231600400004 DETECTOR (FISCH) IONIZATION CHAMBER 1231600400005 MONITOR (1-H-1(N,EL),,SIG) 1231600400006 STATUS (SPSDD,12316010) 1231600400007 HISTORY (800512A)SUBENTRY SUPERSEDED 1231600400008 ENDBIB 6 0 1231600400009 NOCOMMON 0 0 1231600400010 NODATA 0 0 1231600400011 ENDSUBENT 10 0 1231600499999 SUBENT 12316005 19841018 00001231600500001 BIB 5 5 1231600500002 REACTION (92-U-235(N,F),,SIG) 1231600500003 STATUS (SPSDD,12316010) 1231600500004 REFERENCE (J,PR,125,1329,6202) 1231600500005 MONITOR (1-H-1(N,EL)1-H-1,,SIG) 1231600500006 HISTORY (841018U) BIB CORRECTION. 1231600500007 ENDBIB 5 0 1231600500008 COMMON 1 3 1231600500009 DATA-ERR 1231600500010 PER-CENT 1231600500011 5.0 1231600500012 ENDCOMMON 3 0 1231600500013 NODATA 0 0 1231600500014 ENDSUBENT 13 0 1231600599999 SUBENT 12316006 19841018 00001231600600001 BIB 5 5 1231600600002 REACTION (92-U-238(N,F),,SIG) 1231600600003 STATUS (SPSDD,12316011) 1231600600004 DETECTOR (FISCH) BACK-TO-BACK FISSION COUNTER 1231600600005 MONITOR (1-H-1(N,EL)1-H-1,,SIG) 1231600600006 HISTORY (841018U) BIB CORRECTION. 1231600600007 ENDBIB 5 0 1231600600008 NOCOMMON 0 0 1231600600009 NODATA 0 0 1231600600010 ENDSUBENT 9 0 1231600699999 SUBENT 12316007 19800528 00001231600700001 BIB 7 8 1231600700002 REACTION (92-U-238(N,F),,SIG) 1231600700003 REFERENCE (W,SMITH,68) 1231600700004 DETECTOR (FISCH) IONIZATION CHAMBER 1231600700005 MONITOR (1-H-1(N,TOT),,SIG) 1231600700006 ERR-ANALYS (DATA-ERR1) ABSOLUTE ERROR 1231600700007 (DATA-ERR2) STATISTICAL ERROR 1231600700008 STATUS (SPSDD,12316011) 1231600700009 HISTORY (800512A)SUBENTRY SUPERSEDED 1231600700010 ENDBIB 8 0 1231600700011 NOCOMMON 0 0 1231600700012 NODATA 0 0 1231600700013 ENDSUBENT 12 0 1231600799999 SUBENT 12316008 19800528 00001231600800001 BIB 5 6 1231600800002 REACTION (94-PU-239(N,F),,SIG) 1231600800003 STATUS (SPSDD) 1231600800004 DETECTOR (FISCH) IONIZATION CHAMBER 1231600800005 MONITOR (1-H-1(N,TOT),,SIG) 1231600800006 ERR-ANALYS (DATA-ERR1) ABSOLUTE ERROR 1231600800007 (DATA-ERR2) STATISTICAL ERROR 1231600800008 ENDBIB 6 0 1231600800009 COMMON 1 3 1231600800010 DATA-ERR1 1231600800011 PER-CENT 1231600800012 5. 1231600800013 ENDCOMMON 3 0 1231600800014 NODATA 0 0 1231600800015 ENDSUBENT 14 0 1231600899999 SUBENT 12316009 19860512 00001231600900001 BIB 4 4 1231600900002 REACTION (94-PU-239(N,F),,SIG) 1231600900003 DETECTOR (FISCH) DOUBLE IONIZATION CHAMBER 1231600900004 MONITOR (92-U-238(N,F),,SIG) 1231600900005 STATUS DATA TAKEN FROM PRIVATE COMM., SMITH, 61/2. 1231600900006 ENDBIB 4 0 1231600900007 COMMON 1 3 1231600900008 DATA-ERR 1231600900009 PER-CENT 1231600900010 5. 1231600900011 ENDCOMMON 3 0 1231600900012 DATA 2 26 1231600900013 EN DATA 1231600900014 MEV B 1231600900015 2.0 2.11 1231600900016 2.5 2.07 1231600900017 3.0 2.01 1231600900018 3.5 1.97 1231600900019 4.0 1.90 1231600900020 4.5 1.85 1231600900021 5.0 1.83 1231600900022 5.5 1.82 1231600900023 6.0 1.84 1231600900024 6.25 1.98 1231600900025 6.5 2.00 1231600900026 7.0 2.11 1231600900027 7.5 2.22 1231600900028 8.0 2.35 1231600900029 8.5 2.42 1231600900030 9.0 2.43 1231600900031 9.5 2.41 1231600900032 10.0 2.43 1231600900033 12.7 2.70 1231600900034 14.1 2.76 1231600900035 14.8 2.82 1231600900036 16.0 2.85 1231600900037 17.0 2.81 1231600900038 18.0 2.89 1231600900039 19.0 2.96 1231600900040 20.0 3.15 1231600900041 ENDDATA 28 0 1231600900042 ENDSUBENT 41 0 1231600999999 SUBENT 12316010 19860512 00001231601000001 BIB 6 24 1231601000002 REACTION (92-U-235(N,F),,SIG) 1231601000003 DETECTOR (IOCH) PARALLEL PLATE IONIZATION CHAMBER. 1231601000004 MONITOR (1-H-1(N,EL)1-H-1,,SIG) 1231601000005 CORRECTION CORRECTED FOR D(D,NP)D NEUTRONS IN THE ENERGY RANGE 1231601000006 BETWEEN 8 AND 10 MEV. 1231601000007 ERR-ANALYS (DATA-ERR1)STATISTICAL UNCERTAINTY. 1231601000008 (DATA-ERR2) TO THE STATISTICAL UNCERTAINTY ALSO ADD 1231601000009 - 30 PERCENT UNCERTAINTY DUE TO SCATTERING CORRECTION1231601000010 - 30 PERCENT UNCERTAINTY IN SECOND-GROUP NEUTRON 1231601000011 CORRECTIONS. 1231601000012 (IMPORTANT FOR NEUTRONS FROM D-D REACTIONS WITH 1231601000013 INCIDENT ENERGY GREATER THAN 9.5 MEV AND LESS 1231601000014 THAN 11 MEV.) 1231601000015 ( ALSO FOR D-T REACTIONS WITH INCIDENT ENERGIES 1231601000016 GREATER THAN 21 MEV.) 1231601000017 - 3 PERCENT UNCERTAINTY FROM THE FOLLOWING 1231601000018 - UNCERTAINTIES IN FISSION FUEL MASSES AND PROTON 1231601000019 RADIATOR MASSES. 1231601000020 - RECOIL TELESCOPE GEOMETRY. 1231601000021 - HYDROGEN SCATTERING CROSS SECTION 1231601000022 - TAIL CORRECTION TO FISSION COUNTS.(EXTRAPOLATION 1231601000023 OF PULSE-HEIGHT-DISTRIBUTION TO ZERO). 1231601000024 HISTORY (800331C) REVISED DATA RECEIVED FROM G.E.HANSEN, 80/2. 1231601000025 (860512A) ERROR UNITS CORRECTED. 1231601000026 ENDBIB 24 0 1231601000027 NOCOMMON 0 0 1231601000028 DATA 4 27 1231601000029 EN DATA DATA-ERR1 DATA-ERR2 1231601000030 MEV B PER-CENT PER-CENT 1231601000031 2.22 1.301 0.021+02 .060 +02 1231601000032 2.50 1.250 0.006+02 .057 +02 1231601000033 3.00 1.192 0.006+02 .055 +02 1231601000034 4.00 1.128 0.013+02 .054 +02 1231601000035 5.00 1.078 0.015+02 .051 +02 1231601000036 5.46 1.083 0.007+02 .049 +02 1231601000037 6.00 1.101 0.009+02 .049 +02 1231601000038 6.41 1.278 0.011+02 .048 +02 1231601000039 6.97 1.484 0.010+02 .045 +02 1231601000040 7.47 1.637 0.009+02 .044 +02 1231601000041 7.97 1.699 0.008+02 .043 +02 1231601000042 8.47 1.760 0.010+02 .044 +02 1231601000043 8.98 1.770 0.010+02 .047 +02 1231601000044 9.47 1.766 0.008+02 .057 +02 1231601000045 9.98 1.697 0.009+02 .077 +02 1231601000046 10.37 1.660 0.009+02 .099 +02 1231601000047 10.73 1.646 0.013+02 .123 +02 1231601000048 12.2 1.714 0.025+02 .068 +02 1231601000049 13.2 1.908 0.031+02 .056 +02 1231601000050 14.8 2.046 0.010+02 .050 +02 1231601000051 16.0 2.138 0.027+02 .053 +02 1231601000052 16.2 2.109 0.015+02 .048 +02 1231601000053 17.0 2.154 0.013+02 .048 +02 1231601000054 18.0 2.069 0.013+02 .048 +02 1231601000055 19.0 2.008 0.013+02 .048 +02 1231601000056 20.0 1.982 0.013+02 .049 +02 1231601000057 20.5 2.012 0.015+02 .049 +02 1231601000058 ENDDATA 29 0 1231601000059 ENDSUBENT 58 0 1231601099999 SUBENT 12316011 19860512 00001231601100001 BIB 6 24 1231601100002 REACTION (92-U-238(N,F),,SIG) 1231601100003 DETECTOR (IOCH) PARALLEL PLATE IONIZATION CHAMBER. 1231601100004 MONITOR (1-H-1(N,EL)1-H-1,,SIG) 1231601100005 CORRECTION CORRECTED FOR D(D,NP)D NEUTRONS IN THE ENERGY RANGE 1231601100006 BETWEEN 8 AND 10 MEV. 1231601100007 ERR-ANALYS (DATA-ERR1)STATISTICAL UNCERTAINTY. 1231601100008 (DATA-ERR2) TO THE STATISTICAL UNCERTAINTY ALSO ADD 1231601100009 - 30 PERCENT UNCERTAINTY DUE TO SCATTERING CORRECTION1231601100010 - 30 PERCENT UNCERTAINTY IN SECOND-GROUP NEUTRON 1231601100011 CORRECTIONS. 1231601100012 (IMPORTANT FOR NEUTRONS FROM D-D REACTIONS WITH 1231601100013 INCIDENT ENERGY GREATER THAN 9.5 MEV AND LESS 1231601100014 THAN 11 MEV.) 1231601100015 ( ALSO FOR D-T REACTIONS WITH INCIDENT ENERGIES 1231601100016 GREATER THAN 21 MEV.) 1231601100017 - 3 PERCENT UNCERTAINTY FROM THE FOLLOWING 1231601100018 - UNCERTAINTIES IN FISSION FUEL MASSES AND PROTON 1231601100019 RADIATOR MASSES. 1231601100020 - RECOIL TELESCOPE GEOMETRY. 1231601100021 - HYDROGEN SCATTERING CROSS SECTION 1231601100022 - TAIL CORRECTION TO FISSION COUNTS.(EXTRAPOLATION 1231601100023 OF PULSE-HEIGHT-DISTRIBUTION TO ZERO). 1231601100024 HISTORY (800331C) REVISED DATA RECEIVED FROM G.E.HANSEN, 80/2. 1231601100025 (860512A) ERROR UNITS CORRECTED. 1231601100026 ENDBIB 24 0 1231601100027 NOCOMMON 0 0 1231601100028 DATA 4 43 1231601100029 EN DATA DATA-ERR1 DATA-ERR2 1231601100030 MEV B PER-CENT PER-CENT 1231601100031 1.00 0.012 0.006+02 .50 +02 1231601100032 1.205 0.064 0.010+02 .16 +02 1231601100033 1.50 0.334 0.012+02 .053 +02 1231601100034 1.736 0.411 0.018+02 .059 +02 1231601100035 2.00 0.523 0.010+02 .046 +02 1231601100036 2.50 0.515 0.013+02 .054 +02 1231601100037 3.00 0.492 0.012+02 .053 +02 1231601100038 3.50 0.518 0.010+02 .046 +02 1231601100039 4.00 0.524 0.010+02 .046 +02 1231601100040 4.5 0.529 0.010+02 .044 +02 1231601100041 5.0 0.535 0.010+02 .043 +02 1231601100042 5.5 0.543 0.009+02 .041 +02 1231601100043 6.0 0.590 0.009+02 .041 +02 1231601100044 6.5 0.784 0.012+02 .040 +02 1231601100045 7.0 0.920 0.013+02 .039 +02 1231601100046 7.5 0.963 0.014+02 .039 +02 1231601100047 8.0 0.943 0.02 +02 .039 +02 1231601100048 8.5 0.993 0.015+02 .039 +02 1231601100049 9.0 1.014 0.015+02 .039 +02 1231601100050 9.5 0.961 0.027+02 .045 +02 1231601100051 10.0 0.951 0.035+02 .061 +02 1231601100052 10.5 0.918 0.046+02 .079 +02 1231601100053 11.0 0.994 0.072+02 .107 +02 1231601100054 11.9 0.927 0.042+02 .058 +02 1231601100055 12.2 0.973 0.019+02 .042 +02 1231601100056 13.0 1.016 0.021+02 .042 +02 1231601100057 14.1 1.109 0.015+02 .039 +02 1231601100058 14.8 1.249 0.027+02 .042 +02 1231601100059 15.0 1.219 0.016+02 .039 +02 1231601100060 16.0 1.336 0.019+02 .039 +02 1231601100061 16.1 1.310 0.020+02 .039 +02 1231601100062 17.0 1.304 0.020+02 .039 +02 1231601100063 18.0 1.340 0.020+02 .039 +02 1231601100064 19.0 1.350 0.019+02 .039 +02 1231601100065 19.5 1.378 0.032+02 .043 +02 1231601100066 20.0 1.406 0.020+02 .039 +02 1231601100067 20.5 1.462 0.021+02 .039 +02 1231601100068 20.75 1.468 0.032+02 .042 +02 1231601100069 21.0 1.539 0.022+02 .039 +02 1231601100070 21.25 1.467 0.036+02 .044 +02 1231601100071 21.50 1.544 0.032+02 .040 +02 1231601100072 22.00 1.555 0.095+02 .09 +02 1231601100073 22.50 1.741 0.184+02 .16 +02 1231601100074 ENDDATA 45 0 1231601100075 ENDSUBENT 74 0 1231601199999 ENDENTRY 11 0 1231699999999