ENTRY 12834 20130322 13891283400000001 SUBENT 12834001 20130322 13891283400100001 BIB 10 24 1283400100002 TITLE Measurement of the energy dependence of prompt neutron 1283400100003 emission from 233U,235U,239Pu, and 241Pu for E=0.005 1283400100004 to 10 ev relative to emission from spontaneous fission1283400100005 of 252Cf 1283400100006 AUTHOR (R.Gwin, R.R.Spencer, R.W.Ingle) 1283400100007 INSTITUTE (1USAORL) 1283400100008 REFERENCE (J,NSE,87,381,1984) 1283400100009 FACILITY (LINAC,1USAORL) ORELA 1283400100010 METHOD (TOF) 21.65 m flight path 1283400100011 DETECTOR (STANK) Gd-loaded NE213 liquid scintillator tank 1283400100012 (FISCH) Centred in the liquid scinillaotr tank 1283400100013 CORRECTION Corrections were done for 1283400100014 - displacement of samples from centre of detector, 1283400100015 - false fissions, 1283400100016 - deadtime and background of detection system, 1283400100017 - neutron detection efficiency, 1283400100018 - impurity fission, 1283400100019 - delayed gamma rays from fission to detector system. 1283400100020 STATUS (APRVD) R.Gwin, 1984-03-02 1283400100021 (PRELM) 1283400100022 HISTORY (19830829C) 1283400100023 (19840918A) REFERENCE update 1283400100024 (19860528A) BIB update 1283400100025 (20130322U) On. CORRECTION added 1283400100026 ENDBIB 24 0 1283400100027 COMMON 1 3 1283400100028 ERR-2 1283400100029 PER-CENT 1283400100030 0.12 1283400100031 ENDCOMMON 3 0 1283400100032 ENDSUBENT 31 0 1283400199999 SUBENT 12834002 20130322 13891283400200001 BIB 6 25 1283400200002 REACTION ((92-U-235(N,F),PR,NU,,AV)/(98-CF-252(0,F),PR,NU,,AV)) 1283400200003 SAMPLE (92-U-235,ENR=0.9990) 1283400200004 (92-U-234,ENR=0.0003) 1283400200005 (92-U-236,ENR=0.0001) 1283400200006 (92-U-238,ENR=0.0006) 1283400200007 CORRECTION Correction factor applied for differences in the 1283400200008 distribution of fission neutrons between 252Cf 1283400200009 and 235U = 0.9992 1283400200010 ERR-ANALYS (ERR-S) Statistical uncertainty 1283400200011 (ERR-1) Systematic uncertainty due to 1283400200012 - impurity fissions; 1283400200013 - effect of foil thickness; 1283400200014 - effect of delayed gamma-ray. 1283400200015 Uncorrelated among data sets. 1283400200016 (ERR-2) Systematic uncertainty due to 1283400200017 - pulse pileup; 1283400200018 - differences in fission neutron energy 1283400200019 spectrum between isotopes; 1283400200020 - displacement of isotopes from center of 1283400200021 neutron detector. 1283400200022 Fully correlated among data sets. 1283400200023 STATUS (TABLE) Table 3(Data set 3) of Nucl.Sci.Eng.87(1984)3811283400200024 (COREL,12833003) Data set 2 1283400200025 (COREL,12906003) Data set 1 1283400200026 HISTORY (20130322A) On. ERR-ANALYS and ERR-2 moved from 001. 1283400200027 ENDBIB 25 0 1283400200028 COMMON 2 3 1283400200029 ERR-1 ERR-2 1283400200030 PER-CENT PER-CENT 1283400200031 0.06 0.12 1283400200032 ENDCOMMON 3 0 1283400200033 DATA 4 10 1283400200034 EN-MIN EN-MAX DATA ERR-S 1283400200035 EV EV NO-DIM NO-DIM 1283400200036 0.005 0.010 0.6421 0.0063 1283400200037 0.010 0.020 0.6459 0.0033 1283400200038 0.020 0.050 0.6447 0.0019 1283400200039 0.050 0.100 0.6454 0.0022 1283400200040 0.100 0.200 0.6446 0.0034 1283400200041 0.200 0.300 0.6427 0.0051 1283400200042 0.300 0.400 0.6408 0.0066 1283400200043 0.400 0.500 0.6517 0.0096 1283400200044 0.500 1.000 0.6461 0.0069 1283400200045 1.000 10.000 0.6436 0.0050 1283400200046 ENDDATA 12 0 1283400200047 ENDSUBENT 46 0 1283400299999 SUBENT 12834003 20130322 13891283400300001 BIB 6 27 1283400300002 REACTION ((94-PU-241(N,F),PR,NU,,AV)/(98-CF-252(0,F),PR,NU,,AV))1283400300003 SAMPLE (94-PU-241,ENR=0.968) 1283400300004 (94-PU-238,ENR=0.0001) 1283400300005 (94-PU-239,ENR=0.0117) 1283400300006 (94-PU-240,ENR=0.0124) 1283400300007 (94-PU-242,ENR=0.0077) 1283400300008 (94-PU-244,ENR=0.00001) 1283400300009 CORRECTION Correction factor applied for differences in the 1283400300010 distribution of fission neutrons between 252Cf 1283400300011 and 241Pu = 0.9995 1283400300012 Not corrected for effect produced by 239Pu impurity in 1283400300013 sample. 1283400300014 ERR-ANALYS (ERR-S) Statistical uncertainty 1283400300015 (ERR-1) Systematic uncertainty due to 1283400300016 - impurity fissions; 1283400300017 - effect of foil thickness; 1283400300018 - effect of delayed gamma-ray. 1283400300019 Uncorrelated among data sets. 1283400300020 (ERR-2) Systematic uncertainty due to 1283400300021 - pulse pileup; 1283400300022 - differences in fission neutron energy 1283400300023 spectrum between isotopes; 1283400300024 - displacement of isotopes from center of 1283400300025 neutron detector. 1283400300026 Fully correlated among data sets. 1283400300027 STATUS (TABLE) Table 3(Data set 3) of Nucl.Sci.Eng.87(1984)3811283400300028 HISTORY (20130322A) On. ERR-ANALYS and ERR-2 moved from 001. 1283400300029 ENDBIB 27 0 1283400300030 COMMON 2 3 1283400300031 ERR-1 ERR-2 1283400300032 PER-CENT PER-CENT 1283400300033 0.16 0.12 1283400300034 ENDCOMMON 3 0 1283400300035 DATA 4 10 1283400300036 EN-MIN EN-MAX DATA ERR-S 1283400300037 EV EV NO-DIM NO-DIM 1283400300038 0.005 0.010 0.7791 0.0017 1283400300039 0.010 0.020 0.7831 0.0013 1283400300040 0.020 0.050 0.7819 0.0006 1283400300041 0.050 0.100 0.7824 0.0008 1283400300042 0.100 0.200 0.7824 0.0008 1283400300043 0.200 0.300 0.7810 0.0008 1283400300044 0.300 0.400 0.7791 0.0017 1283400300045 0.400 0.500 0.7856 0.0041 1283400300046 0.500 1.000 0.7750 0.0038 1283400300047 1.000 10.000 0.7832 0.0011 1283400300048 ENDDATA 12 0 1283400300049 ENDSUBENT 48 0 1283400399999 SUBENT 12834004 20130322 13891283400400001 BIB 6 17 1283400400002 REACTION (94-PU-241(N,F),NUM,NU,,AV) 1283400400003 ADD-RES =2.951 +/- 0.005 1283400400004 var(nu)=1.340 1283400400005 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1283400400006 (ERR-1) Uncertainty due to neutron detection efficiency1283400400007 (ERR-2) Uncertainty due to pileup parameter 1283400400008 COVARIANCE Correlation coefficients between multiplicities 1283400400009 100 1283400400010 -42 100 1283400400011 21 -39 100 1283400400012 -9 21 -67 100 1283400400013 -5 -20 13 -65 100 1283400400014 -5 -11 -17 25 -51 100 1283400400015 -1 -7 -3 -6 27 -53 100 1283400400016 0 -1 -1 1 -3 21 -54 100 1283400400017 STATUS (TABLE) Table VII of Nucl.Sci.Eng.87(1984)381 1283400400018 HISTORY (20130322C) LV+On 1283400400019 ENDBIB 17 0 1283400400020 COMMON 4 3 1283400400021 EN-MIN EN-MAX ERR-1 ERR-2 1283400400022 EV EV PER-CENT PER-CENT 1283400400023 0.02 0.1 0.15 3.8 1283400400024 ENDCOMMON 3 0 1283400400025 DATA 3 8 1283400400026 PART-OUT DATA DATA-ERR 1283400400027 NO-DIM NO-DIM NO-DIM 1283400400028 0. 0.0098 0.0005 1283400400029 1. 0.0853 0.0016 1283400400030 2. 0.2613 0.0026 1283400400031 3. 0.3352 0.0028 1283400400032 4. 0.2205 0.0025 1283400400033 5. 0.0735 0.0016 1283400400034 6. 0.0134 0.0007 1283400400035 7. 0.0011 0.0003 1283400400036 ENDDATA 10 0 1283400400037 ENDSUBENT 36 0 1283400499999 SUBENT 12834005 20130322 13891283400500001 BIB 6 6 1283400500002 REACTION (94-PU-241(N,F),,NU,,AV) 1283400500003 MONITOR (98-CF-252(0,F),,NU) 1283400500004 MONIT-REF (10954002,R.R.Spencer+,J,NSE,80,603,1982) 1283400500005 ERR-ANALYS (DATA-ERR) No information on source of uncertainty 1283400500006 STATUS (TABLE) Table VII of Nucl.Sci.Eng.87(1984)381 1283400500007 HISTORY (20130322C) On 1283400500008 ENDBIB 6 0 1283400500009 NOCOMMON 0 0 1283400500010 DATA 6 1 1283400500011 EN-MIN EN-MAX DATA DATA-ERR MONIT MONIT-ERR 1283400500012 EV EV PRT/FIS PRT/FIS PRT/FIS PRT/FIS 1283400500013 0.02 0.1 2.951 0.005 3.773 0.007 1283400500014 ENDDATA 3 0 1283400500015 ENDSUBENT 14 0 1283400599999 ENDENTRY 5 0 1283499999999