ENTRY 14387 20140519 14001438700000001 SUBENT 14387001 20140519 14001438700100001 BIB 5 6 1438700100002 TITLE The Prompt Radiations in the Spontaneous Fission of 1438700100003 Californium-252 1438700100004 AUTHOR (H.R.Bowman,S.G.Thompson) 1438700100005 REFERENCE (C,58GENEVA,15,212,1958) 1438700100006 INSTITUTE (1USALRL,1USABRK) 1438700100007 HISTORY (20140519C) BP 1438700100008 ENDBIB 6 0 1438700100009 NOCOMMON 0 0 1438700100010 ENDSUBENT 9 0 1438700199999 SUBENT 14387002 20140519 14001438700200001 BIB 5 6 1438700200002 REACTION (98-CF-252(0,F),PR,NU) 1438700200003 DETECTOR (STANK) Cylindrical tank of Cd-loaded scintillator, 1438700200004 36 in. in diameter and 36 in. high. 1438700200005 METHOD Neutrons were detected with liquid scintillator. 1438700200006 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 1438700200007 STATUS (TABLE) page 212. 1438700200008 ENDBIB 6 0 1438700200009 NOCOMMON 0 0 1438700200010 DATA 2 1 1438700200011 DATA DATA-ERR 1438700200012 PRT/FIS PRT/FIS 1438700200013 3.8 0.16 1438700200014 ENDDATA 3 0 1438700200015 ENDSUBENT 14 0 1438700299999 SUBENT 14387003 20140519 14001438700300001 BIB 5 13 1438700300002 REACTION (98-CF-252(0,F)MASS,IND,FY) The mass ratio 1438700300003 distribution for 252Cf. 1438700300004 DETECTOR (FISCH) 1438700300005 METHOD (COINC) A weightless amount of 252Cf was volatilized 1438700300006 on to a 5 microg/cm2 plastic film and was placed 1438700300007 between the two halves of a two-sided Frisch-gridded 1438700300008 ionization detector. The ionization produced by the 1438700300009 two fission fragments was measured and recorded in 1438700300010 time coincidence. 1438700300011 CORRECTION All energy measurements have been corrected to 1438700300012 include ionization defect. This correction is ~7% 1438700300013 for all energies. 1438700300014 STATUS (CURVE) Fig. 2, page 213. 1438700300015 ENDBIB 13 0 1438700300016 NOCOMMON 0 0 1438700300017 DATA 2 17 1438700300018 MASS-RATIO DATA 1438700300019 NO-DIM PC/FIS 1438700300020 1.051 1.506 1438700300021 1.104 2.392 1438700300022 1.156 3.581 1438700300023 1.205 4.972 1438700300024 1.232 5.536 1438700300025 1.258 5.958 1438700300026 1.279 6.220 1438700300027 1.355 6.498 1438700300028 1.384 6.193 1438700300029 1.405 5.363 1438700300030 1.455 4.168 1438700300031 1.551 1.940 1438700300032 1.629 1.087 1438700300033 1.677 0.741 1438700300034 1.748 0.353 1438700300035 1.806 0.167 1438700300036 1.851 0.064 1438700300037 ENDDATA 19 0 1438700300038 ENDSUBENT 37 0 1438700399999 SUBENT 14387004 20140519 14001438700400001 BIB 6 17 1438700400002 REACTION (98-CF-252(0,F),PR,NU/TKE) The average number of 1438700400003 neutrons per fission as a function of total kinetic 1438700400004 energy. 1438700400005 PART-DET (N) 1438700400006 DETECTOR (STANK,FISCH) A cylindrical tank of cadmium-loaded 1438700400007 liquid scintillator, 36 in. in diameter by 36-in. high.1438700400008 METHOD (COINC) The spontaneous fission source was located in 1438700400009 the center of the tank. The fission neutrons were 1438700400010 moderated and captured by the liquid scintillator 1438700400011 with a mean life of 10 microseconds. The two-sided 1438700400012 ionization chamber containing the weightless 252Cf 1438700400013 sample was placed in the scintillation tank. The 1438700400014 fission-fragment kinetic energies and the number of 1438700400015 neutrons were read from film and the data were 1438700400016 punched into IBM cards. 1438700400017 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 1438700400018 STATUS (CURVE) Fig.4, page 214. 1438700400019 ENDBIB 17 0 1438700400020 NOCOMMON 0 0 1438700400021 DATA 4 9 1438700400022 TKE DATA +DATA-ERR -DATA-ERR 1438700400023 MEV PRT/FIS PRT/FIS PRT/FIS 1438700400024 135.799 4.705 0.341 0.998 1438700400025 145.316 4.436 0.347 0.389 1438700400026 155.130 4.394 0.179 0.179 1438700400027 165.242 4.436 0.132 0.132 1438700400028 175.353 4.173 0.090 0.072 1438700400029 185.167 3.815 0.060 0.072 1438700400030 195.279 3.145 0.066 0.072 1438700400031 205.390 2.631 0.120 0.155 1438700400032 214.610 1.172 0.173 0.018 1438700400033 ENDDATA 11 0 1438700400034 ENDSUBENT 33 0 1438700499999 SUBENT 14387005 20140519 14001438700500001 BIB 6 17 1438700500002 REACTION (98-CF-252(0,F)MASS,PR,NU) The average number of 1438700500003 neutrons per fission for different mass ratios of 1438700500004 252Cf. 1438700500005 PART-DET (N) 1438700500006 DETECTOR (STANK,FISCH) A cylindrical tank of cadmium-loaded 1438700500007 liquid scintillator, 36 in. in diameter by 36-in. high.1438700500008 METHOD (COINC) The spontaneous fission source was located in 1438700500009 the center of the tank. The fission neutrons were 1438700500010 moderated and captured by the liquid scintillator 1438700500011 with a mean life of 10 microseconds. The two-sided 1438700500012 ionization chamber containing the weightless 252Cf 1438700500013 sample was place in the scintillation tank. The 1438700500014 fission-fragment kinetic energies and the number of 1438700500015 neutrons were read from film and the data were 1438700500016 punched into IBM cards. 1438700500017 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 1438700500018 STATUS (CURVE) Fig.5, page 214. 1438700500019 ENDBIB 17 0 1438700500020 NOCOMMON 0 0 1438700500021 DATA 4 12 1438700500022 MASS-RATIO DATA +DATA-ERR -DATA-ERR 1438700500023 NO-DIM PRT/FIS PRT/FIS PRT/FIS 1438700500024 1.047 4.000 0.124 0.149 1438700500025 1.148 4.040 0.074 0.083 1438700500026 1.246 3.849 0.083 0.066 1438700500027 1.349 3.749 0.074 0.074 1438700500028 1.441 3.591 0.091 0.058 1438700500029 1.546 3.648 0.107 0.083 1438700500030 1.649 3.763 0.116 0.124 1438700500031 1.749 3.671 0.116 0.157 1438700500032 1.848 3.646 0.298 0.240 1438700500033 1.948 3.860 0.504 0.496 1438700500034 2.047 3.462 0.595 0.595 1438700500035 2.152 3.875 0.777 0.810 1438700500036 ENDDATA 14 0 1438700500037 ENDSUBENT 36 0 1438700599999 SUBENT 14387006 20140519 14001438700600001 BIB 4 6 1438700600002 REACTION 1(98-CF-252(0,F)0-G-0,PR,FY) Photon emission in 1438700600003 spontaneous fission. 1438700600004 2(98-CF-252(0,F)0-G-0,PR,KE) 1438700600005 DETECTOR (NAICR,FISCH) 1438700600006 REL-REF (A,14320001,A.B.Smith+,J,PR,104,699,1956) 1438700600007 STATUS (TABLE) page 213. 1438700600008 ENDBIB 6 0 1438700600009 NOCOMMON 0 0 1438700600010 DATA 2 1 1438700600011 DATA 1DATA 2 1438700600012 PRT/FIS MEV 1438700600013 10.0 9.0 1438700600014 ENDDATA 3 0 1438700600015 ENDSUBENT 14 0 1438700699999 SUBENT 14387007 20140519 14001438700700001 BIB 7 14 1438700700002 REACTION (98-CF-252(0,F)0-G-0,PR/PAR,FY) The gamma-ray spectrum 1438700700003 in coincidence with the spontaneous fission of 252Cf. 1438700700004 REL-REF (A,14320001,A.B.Smith+,J,PR,104,699,1956) 1438700700005 PART-DET (G) 1438700700006 DETECTOR (NAICR,FISCH) 1438700700007 METHOD (COINC) The gamma-ray spectrum in coincidence with 1438700700008 the spontaneous fission of 252Cf was measured with a 1438700700009 NaI(Tl) spectrometer and an ionization chamber. Care 1438700700010 was taken to correct for or to eliminate the 1438700700011 simultaneous detection of two or more gamma rays per 1438700700012 fission event. For this reason the gamma-ray 1438700700013 detection efficiency was limited to 0.5%. 1438700700014 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 1438700700015 STATUS (CURVE) Fig.6, page 214. 1438700700016 ENDBIB 14 0 1438700700017 NOCOMMON 0 0 1438700700018 DATA 3 14 1438700700019 E DATA DATA-ERR 1438700700020 MEV PRT/FIS PRT/FIS 1438700700021 0.058 8.939E-03 1438700700022 0.120 7.863E-03 1438700700023 0.181 6.917E-03 1438700700024 0.259 5.616E-03 1438700700025 0.405 3.363E-03 1438700700026 0.506 2.181E-03 2.930E-04 1438700700027 0.653 1.225E-03 1438700700028 0.761 7.821E-04 1438700700029 1.000 3.454E-04 1438700700030 1.247 2.135E-04 1438700700031 1.510 1.320E-04 1438700700032 2.004 7.066E-05 1438700700033 2.506 3.222E-05 1438700700034 2.992 1.541E-05 5.089E-06 1438700700035 ENDDATA 16 0 1438700700036 ENDSUBENT 35 0 1438700799999 SUBENT 14387008 20140519 14001438700800001 BIB 6 13 1438700800002 REACTION (98-CF-252(0,F),PR,NU/DE,,REL) The energy distribution 1438700800003 of prompt neutrons from 252Cf. 1438700800004 PART-DET (N) 1438700800005 DETECTOR (SCIN) 1438700800006 METHOD (TOF,COINC) The neutron energy distribution was 1438700800007 measured from 300 keV to 8 MeV using a time-of-flight 1438700800008 technique. The fission events were detected in an 1438700800009 argon gas scintillator. The neutrons were detected in 1438700800010 a 2 in. x 2 in. stilbene crystal. The neutron 1438700800011 detector was located one meter from the spontaneous 1438700800012 fission source. 1438700800013 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 1438700800014 STATUS (CURVE) Fig.7, page 214. 1438700800015 ENDBIB 13 0 1438700800016 NOCOMMON 0 0 1438700800017 DATA 3 14 1438700800018 E DATA DATA-ERR 1438700800019 MEV ARB-UNITS ARB-UNITS 1438700800020 0.419 2.918E+02 2.753E+01 1438700800021 0.663 3.362E+02 1.399E+01 1438700800022 0.957 3.509E+02 1.932E+01 1438700800023 1.348 3.364E+02 1.852E+01 1438700800024 1.569 3.047E+02 1.678E+01 1438700800025 1.961 2.572E+02 1.416E+01 1438700800026 2.328 2.140E+02 1.178E+01 1438700800027 2.672 1.706E+02 7.095E+00 1438700800028 3.309 1.215E+02 6.690E+00 1438700800029 3.775 7.837E+01 4.316E+00 1438700800030 4.044 7.620E+01 4.195E+00 1438700800031 4.828 4.579E+01 2.521E+00 1438700800032 5.882 2.601E+01 3.111E+00 1438700800033 8.014 8.272E+00 2.299E+00 1438700800034 ENDDATA 16 0 1438700800035 ENDSUBENT 34 0 1438700899999 ENDENTRY 8 0 1438799999999