ENTRY 10612 20110927 13751061200000001 SUBENT 10612001 20110927 13751061200100001 BIB 9 21 1061200100002 INSTITUTE (1USAANL) 1061200100003 REFERENCE (J,PR,157,1076,196705) 1061200100004 AUTHOR (J.W.Meadows) 1061200100005 TITLE 252Cf Fission Neutron Spectrum from 0.003 to 15.0 MeV. 1061200100006 METHOD (TOF) Time-of-flight 1061200100007 ANALYSIS Li-glass and liquid scintillator detector measurements 1061200100008 were used to determine specrtum shapes in 6 data sets. 1061200100009 Each set was normalised, then they were combined using 1061200100010 a fit in overlapping energy ranges and the combined 1061200100011 spectrum normalised again and the separate data sets 1061200100012 are presented. 1061200100013 CORRECTION Data corrected for multiple scattering, and random, 1061200100014 scattered and delayed gamma background. 1061200100015 STATUS No reply to author proof. 1061200100016 (TABLE) Data taken from private comm., Meadows, 1976/5.1061200100017 HISTORY (19760526C) 1061200100018 (19831014A) Converted to REACTION formalism 1061200100019 (20040726A) Converted to new date formats, lower case. 1061200100020 (20091007A) Subentry 8 correction. 1061200100021 (20110915A) OS. ANALYSIS added. Reaction code and units1061200100022 in subs.2-7 changed. 1061200100023 ENDBIB 21 0 1061200100024 NOCOMMON 0 0 1061200100025 ENDSUBENT 24 0 1061200199999 SUBENT 10612002 20110927 13751061200200001 BIB 5 13 1061200200002 REACTION (98-CF-252(0,F),,NU/DE,,RRE/REL) 1061200200003 Data given is neutron spectrum, normalized to 1061200200004 probability distribution, divided by the square root 1061200200005 of the energy (1/(MeV**1.5)/fission). 1061200200006 DETECTOR (GLASD) 6Li glass detector 1061200200007 Flight path = 18.6 cm. 1061200200008 MONITOR (3-LI-6(N,T)2-HE-4,,SIG) 1061200200009 (92-U-235(N,F),,SIG) 1061200200010 Used to determine detector efficiencies. 1061200200011 ERR-ANALYS (ERR-S) Data errors given are statistical errors. If 1061200200012 no error is given, the statistical error is <5%. 1061200200013 HISTORY (20110915A) OS. REACTION corr., units changed to 1061200200014 ARB-UNITS 1061200200015 ENDBIB 13 0 1061200200016 NOCOMMON 0 0 1061200200017 DATA 3 21 1061200200018 E DATA ERR-S 1061200200019 MEV ARB-UNITS ARB-UNITS 1061200200020 0.2810E-02 0.1182E+01 0.6250E+00 1061200200021 0.3540E-02 0.9420E+00 0.4570E+00 1061200200022 0.4470E-02 0.1158E+01 0.7520E+00 1061200200023 0.5630E-02 0.1057E+01 0.2650E+00 1061200200024 0.7110E-02 0.9520E+00 0.2210E+00 1061200200025 0.8970E-02 0.7180E+00 0.1420E+00 1061200200026 0.1120E-01 0.8900E+00 0.1050E+00 1061200200027 0.1420E-01 0.8040E+00 0.0800E+00 1061200200028 0.1790E-01 0.8130E+00 1061200200029 0.2260E-01 0.7270E+00 1061200200030 0.2820E-01 0.7610E+00 1061200200031 0.3560E-01 0.7370E+00 1061200200032 0.4520E-01 0.6940E+00 1061200200033 0.5620E-01 0.7940E+00 1061200200034 0.6980E-01 0.7320E+00 1061200200035 0.8920E-01 0.7420E+00 1061200200036 0.1180E+00 0.7940E+00 1061200200037 0.1370E+00 0.7580E+00 1061200200038 0.1620E+00 0.7080E+00 1061200200039 0.1940E+00 0.6740E+00 1061200200040 0.2380E+00 0.6320E+00 1061200200041 ENDDATA 23 0 1061200200042 ENDSUBENT 41 0 1061200299999 SUBENT 10612003 20110927 13751061200300001 BIB 5 13 1061200300002 REACTION (98-CF-252(0,F),,NU/DE,,RRE/REL) 1061200300003 Data given is neutron spectrum, normalized to 1061200300004 probability distribution, divided by the square root 1061200300005 of the energy (1/(MeV**1.5)/fission). 1061200300006 DETECTOR (GLASD) 6Li glass detector 1061200300007 Flight path = 32.7 cm. 1061200300008 MONITOR (3-LI-6(N,T)2-HE-4,,SIG) 1061200300009 (92-U-235(N,F),,SIG) 1061200300010 Used to determine detector efficiencies. 1061200300011 ERR-ANALYS (ERR-S) Data errors given are statistical errors. If 1061200300012 no error is given, the statistical error is <5%. 1061200300013 HISTORY (20110915A) OS. REACTION corr., units changed to 1061200300014 ARB-UNITS 1061200300015 ENDBIB 13 0 1061200300016 NOCOMMON 0 0 1061200300017 DATA 3 26 1061200300018 E DATA ERR-S 1061200300019 MEV ARB-UNITS ARB-UNITS 1061200300020 0.7050E-02 0.5880E+00 0.3400E+00 1061200300021 0.8880E-02 0.5930E+00 0.2680E+00 1061200300022 0.1120E-01 0.7270E+00 0.1880E+00 1061200300023 0.1420E-01 0.7460E+00 0.1360E+00 1061200300024 0.1800E-01 0.7750E+00 0.9600E-01 1061200300025 0.2240E-01 0.7700E+00 0.7500E-01 1061200300026 0.2820E-01 0.6750E+00 0.5500E-01 1061200300027 0.3580E-01 0.7800E+00 0.3700E-01 1061200300028 0.4480E-01 0.7270E+00 0.3300E-01 1061200300029 0.5620E-01 0.6980E+00 1061200300030 0.7080E-01 0.7030E+00 1061200300031 0.8870E-01 0.7560E+00 1061200300032 0.1120E+00 0.7560E+00 1061200300033 0.1450E+00 0.6890E+00 1061200300034 0.2140E+00 0.6510E+00 1061200300035 0.2790E+00 0.5740E+00 1061200300036 0.3480E+00 0.4930E+00 1061200300037 0.4470E+00 0.4300E+00 1061200300038 0.5680E+00 0.3890E+00 1061200300039 0.7010E+00 0.3640E+00 1061200300040 0.8880E+00 0.3040E+00 1061200300041 0.1162E+01 0.2550E+00 1061200300042 0.1454E+01 0.2090E+00 1061200300043 0.1719E+01 0.1860E+00 1061200300044 0.2063E+01 0.1500E+00 1061200300045 0.2523E+01 0.1200E+00 1061200300046 ENDDATA 28 0 1061200300047 ENDSUBENT 46 0 1061200399999 SUBENT 10612004 20110927 13751061200400001 BIB 5 13 1061200400002 REACTION (98-CF-252(0,F),,NU/DE,,RRE/REL) 1061200400003 Data given is neutron spectrum, normalized to 1061200400004 probability distribution, divided by the square root 1061200400005 of the energy (1/(MeV**1.5)/fission). 1061200400006 DETECTOR (GLASD) 6Li glass detector 1061200400007 Flight path = 134.2 cm. 1061200400008 MONITOR (3-LI-6(N,T)2-HE-4,,SIG) 1061200400009 (92-U-235(N,F),,SIG) 1061200400010 Used to determine detector efficiencies. 1061200400011 ERR-ANALYS (ERR-S) Data errors given are statistical errors. If 1061200400012 no error is given, the statistical error is <5%. 1061200400013 HISTORY (20110915A) OS. REACTION corr., units changed to 1061200400014 ARB-UNITS 1061200400015 ENDBIB 13 0 1061200400016 NOCOMMON 0 0 1061200400017 DATA 3 15 1061200400018 E DATA ERR-S 1061200400019 MEV ARB-UNITS ARB-UNITS 1061200400020 0.1100E+00 0.6550E+00 0.1700E-01 1061200400021 0.1430E+00 0.6360E+00 0.1100E-01 1061200400022 0.1810E+00 0.5640E+00 0.5000E-01 1061200400023 0.2230E+00 0.6170E+00 0.3100E-01 1061200400024 0.2790E+00 0.6090E+00 0.1900E-01 1061200400025 0.3580E+00 0.5170E+00 1061200400026 0.4430E+00 0.5170E+00 1061200400027 0.5430E+00 0.4520E+00 1061200400028 0.6810E+00 0.3590E+00 1061200400029 0.8810E+00 0.2850E+00 1061200400030 0.1124E+01 0.2440E+00 1061200400031 0.1398E+01 0.2260E+00 1061200400032 0.1786E+01 0.1620E+00 1061200400033 0.2186E+01 0.1540E+00 1061200400034 0.2538E+01 0.1290E+00 1061200400035 ENDDATA 17 0 1061200400036 ENDSUBENT 35 0 1061200499999 SUBENT 10612005 20110927 13751061200500001 BIB 5 12 1061200500002 REACTION (98-CF-252(0,F),,NU/DE,,RRE/REL) 1061200500003 Data given is neutron spectrum, normalized to 1061200500004 probability distribution, divided by the square root 1061200500005 of the energy (1/(MeV**1.5)/fission). 1061200500006 DETECTOR (SCIN) Hydrogenous liquid scintillator 1061200500007 Flight path = 138.6 cm. Detector discriminator bias 1061200500008 set at 0.85 MeV. 1061200500009 MONITOR (1-H-1(N,EL)1-H-1,,SIG) n,p cross section used to 1061200500010 determine detector efficiency. 1061200500011 ERR-ANALYS No information on uncertainties. 1061200500012 HISTORY (20110915A) OS. REACTION corr., units changed to 1061200500013 ARB-UNITS 1061200500014 ENDBIB 12 0 1061200500015 NOCOMMON 0 0 1061200500016 DATA 2 15 1061200500017 E DATA 1061200500018 MEV ARB-UNITS 1061200500019 0.1106E+01 0.2830E+00 1061200500020 0.1393E+01 0.2330E+00 1061200500021 0.1704E+01 0.1860E+00 1061200500022 0.2162E+01 0.1380E+00 1061200500023 0.2677E+01 0.9950E-01 1061200500024 0.3272E+01 0.7080E-01 1061200500025 0.3815E+01 0.4950E-01 1061200500026 0.4227E+01 0.3780E-01 1061200500027 0.4540E+01 0.3210E-01 1061200500028 0.4896E+01 0.2580E-01 1061200500029 0.5292E+01 0.1990E-01 1061200500030 0.5739E+01 0.1510E-01 1061200500031 0.6388E+01 0.1220E-01 1061200500032 0.6820E+01 0.8280E-02 1061200500033 0.7479E+01 0.5500E-02 1061200500034 ENDDATA 17 0 1061200500035 ENDSUBENT 34 0 1061200599999 SUBENT 10612006 20110927 13751061200600001 BIB 5 13 1061200600002 REACTION (98-CF-252(0,F),,NU/DE,,RRE/REL) 1061200600003 Data given is neutron spectrum, normalized to 1061200600004 probability distribution, divided by the square root 1061200600005 of the energy (1/(MeV**1.5)/fission). 1061200600006 DETECTOR (SCIN) Hydrogenous liquid scintillator 1061200600007 Flight path = 138.6 cm. Detector discriminator bias 1061200600008 set at 4.0 MeV. 1061200600009 MONITOR (1-H-1(N,EL)1-H-1,,SIG) n,p cross section used to 1061200600010 determine detector efficiency. 1061200600011 ERR-ANALYS (ERR-S) Data errors given are statistical errors. If 1061200600012 no error is given, the statistical error is <5%. 1061200600013 HISTORY (20110915A) OS. REACTION corr., units changed to 1061200600014 ARB-UNITS 1061200600015 ENDBIB 13 0 1061200600016 NOCOMMON 0 0 1061200600017 DATA 3 12 1061200600018 E DATA ERR-S 1061200600019 MEV ARB-UNITS ARB-UNITS 1061200600020 0.4580E+01 0.3110E-01 1061200600021 0.4950E+01 0.2380E-01 1061200600022 0.5340E+01 0.1970E-01 1061200600023 0.5790E+01 0.1440E-01 1061200600024 0.6300E+01 0.9520E-02 1061200600025 0.6890E+01 0.7080E-02 1061200600026 0.7550E+01 0.4390E-02 1061200600027 0.8320E+01 0.2940E-02 1061200600028 0.9200E+01 0.1640E-02 0.1100E-03 1061200600029 0.1025E+02 0.8850E-03 0.7200E-04 1061200600030 0.1148E+02 0.3740E-03 0.5200E-04 1061200600031 0.1294E+02 0.1020E-03 0.3000E-04 1061200600032 ENDDATA 14 0 1061200600033 ENDSUBENT 32 0 1061200699999 SUBENT 10612007 20110927 13751061200700001 BIB 5 13 1061200700002 REACTION (98-CF-252(0,F),,NU/DE,,RRE/REL) 1061200700003 Data given is neutron spectrum, normalized to 1061200700004 probability distribution, divided by the square root 1061200700005 of the energy (1/(MeV**1.5)/fission). 1061200700006 DETECTOR (SCIN) Hydrogenous liquid scintillator 1061200700007 Flight path = 138.6 cm. Detector discriminator bias 1061200700008 set at 6.50 MeV 1061200700009 MONITOR (1-H-1(N,EL)1-H-1,,SIG) n,p cross section used to 1061200700010 determine detector efficiency. 1061200700011 ERR-ANALYS (ERR-S) Data errors given are statistical errors. If 1061200700012 no error is given, the statistical error is <5%. 1061200700013 HISTORY (20110915A) OS. REACTION corr., units changed to 1061200700014 ARB-UNITS 1061200700015 ENDBIB 13 0 1061200700016 NOCOMMON 0 0 1061200700017 DATA 3 9 1061200700018 E DATA ERR-S 1061200700019 MEV ARB-UNITS ARB-UNITS 1061200700020 0.7070E+01 0.5790E-02 1061200700021 0.7760E+01 0.3880E-02 1061200700022 0.8550E+01 0.2820E-02 1061200700023 0.9470E+01 0.1380E-02 0.1200E-03 1061200700024 0.1056E+02 0.8370E-03 0.8400E-04 1061200700025 0.1183E+02 0.3430E-03 0.4800E-04 1061200700026 0.1336E+02 0.2170E-04 0.3600E-05 1061200700027 0.1521E+02 0.6840E-05 0.2200E-05 1061200700028 0.1810E+02 0.1960E-05 0.1000E-05 1061200700029 ENDDATA 11 0 1061200700030 ENDSUBENT 29 0 1061200799999 SUBENT 10612008 20091008 13571061200800001 BIB 3 3 1061200800002 REACTION (98-CF-252(0,F)0-NN-1,,KE) 1061200800003 ERR-ANALYS No information on uncertainties. 1061200800004 HISTORY (20091007A) Reaction corrected. 1061200800005 ENDBIB 3 0 1061200800006 NOCOMMON 0 0 1061200800007 DATA 1 1 1061200800008 DATA 1061200800009 MEV 1061200800010 2.348 1061200800011 ENDDATA 3 0 1061200800012 ENDSUBENT 11 0 1061200899999 ENDENTRY 8 0 1061299999999