ENTRY 12322 20180523 14411232200000001 SUBENT 12322001 20180523 14411232200100001 BIB 8 20 1232200100002 TITLE Direct measurement of the energy variation of eta for 1232200100003 U233, U235, and PU239 1232200100004 AUTHOR (H.Palevsky,D.J.Hughes,R.L.Zimmerman,R.M.Eisberg) 1232200100005 REFERENCE (J,JNE,3,177,1956) 1232200100006 #doi:10.1016/0891-3919(56)90071-7 1232200100007 INSTITUTE (1USABNL) 1232200100008 FACILITY (CHOPS,1USABNL) Brookhaven slow chopper. 1232200100009 DETECTOR (HORBU,BF3) The fission neutrons were detected by 1232200100010 means of proton recoils in a suspension of ZnS in 1232200100011 lucite. This phosphor mixture is molded in the form of 1232200100012 2 in.-diameter "buttons" approximately 1.5 in. in 1232200100013 length. A thin-walled BF3 counter, which gives the 1232200100014 distribution in energy for slow neutrons. 1232200100015 METHOD (TOF) Time-of-flight. 1232200100016 HISTORY (19760804T) Translated from SCISRS. 1232200100017 (19841005A) Converted to reaction formalism. 1232200100018 (20180523U) BP: Updated to new date formats, lower 1232200100019 case. Corrections according last EXFOR rules1232200100020 and Dict. Added doi, extensive experimental1232200100021 details. 1232200100022 ENDBIB 20 0 1232200100023 NOCOMMON 0 0 1232200100024 ENDSUBENT 23 0 1232200199999 SUBENT 12322002 20180523 14411232200200001 BIB 6 12 1232200200002 REACTION (92-U-233(N,ABS),,ETA) 1232200200003 SAMPLE The foil was made of uranium metal with 233U content 1232200200004 greater than 90% and a thickness of 0.025 in. 1232200200005 MONITOR (92-U-233(N,ABS),,ETA) Measurements were normalized to 1232200200006 eta=2.31 at thermal energy. 1232200200007 ERR-ANALYS (ERR-S) The statistical accuracy of data points is 1232200200008 about 1% from 0.01 to 0.1 eV; while fission cross 1232200200009 sections errors are as large as 5%. 1232200200010 CORRECTION The corrections for isotopic impurities, scattering, 1232200200011 and the departure of BF3 counters from 1/v were each 1232200200012 about 1%. 1232200200013 STATUS (SCSRS) Also shown in Fig. 3, page 183. 1232200200014 ENDBIB 12 0 1232200200015 COMMON 2 3 1232200200016 EN-NRM MONIT 1232200200017 EV PRT/INC 1232200200018 0.0253 2.31 1232200200019 ENDCOMMON 3 0 1232200200020 DATA 3 14 1232200200021 EN DATA ERR-S 1232200200022 MEV PRT/INC PRT/INC 1232200200023 1.04E-08 2.285 1.0E-02 1232200200024 1.49E-08 2.300 7.E-03 1232200200025 1.73E-08 2.305 1.0E-02 1232200200026 2.09E-08 2.28 1.E-02 1232200200027 2.50E-08 2.280 1.3E-02 1232200200028 2.91E-08 2.283 1.5E-02 1232200200029 3.50E-08 2.303 1.3E-02 1232200200030 4.60E-08 2.295 1.4E-02 1232200200031 5.70E-08 2.293 1.0E-02 1232200200032 6.50E-08 2.313 1.1E-02 1232200200033 7.1E-08 2.285 1.5E-02 1232200200034 8.0E-08 2.29 2.E-02 1232200200035 9.1E-08 2.275 1.5E-02 1232200200036 9.9E-08 2.275 1.5E-02 1232200200037 ENDDATA 16 0 1232200200038 ENDSUBENT 37 0 1232200299999 SUBENT 12322003 20180523 14411232200300001 BIB 6 15 1232200300002 REACTION (92-U-235(N,ABS),,ETA) 1232200300003 SAMPLE The foils used were made of uranium metal enriched in 1232200300004 235U to a concentration higher than 90% and also 1232200300005 contained minor amounts of 238U and 234U. Two sample 1232200300006 thicknesses were used, 0.030 and 0.045 in. 1232200300007 MONITOR (92-U-235(N,ABS),,ETA) The Brookhaven data are 1232200300008 normalized to eta=2.08 at thermal energy. 1232200300009 ERR-ANALYS (ERR-S,1.,3.) The statistical accuracy of data points 1232200300010 varies from about 1% in the thermal region to about 1232200300011 3% at 0.16 eV. 1232200300012 CORRECTION The correction applied to the data: departure of BF3 1232200300013 counter from 1/v, about 1.2%; 234U and 238U 1232200300014 impurities, about 3.5%; and scattering correction, 1232200300015 about 0.7%. 1232200300016 STATUS (SCSRS) Also shown in Fig. 2, page 182. 1232200300017 ENDBIB 15 0 1232200300018 COMMON 2 3 1232200300019 EN-NRM MONIT 1232200300020 EV PRT/INC 1232200300021 0.0253 2.08 1232200300022 ENDCOMMON 3 0 1232200300023 DATA 2 20 1232200300024 EN DATA 1232200300025 MEV PRT/INC 1232200300026 1.02E-08 2.070 1232200300027 1.52E-08 2.075 1232200300028 2.19E-08 2.077 1232200300029 2.56E-08 2.082 1232200300030 3.12E-08 2.075 1232200300031 3.86E-08 2.090 1232200300032 4.80E-08 2.102 1232200300033 6.08E-08 2.100 1232200300034 6.70E-08 2.120 1232200300035 7.20E-08 2.120 1232200300036 8.00E-08 2.125 1232200300037 8.75E-08 2.108 1232200300038 9.80E-08 2.117 1232200300039 1.03E-07 2.114 1232200300040 1.10E-07 2.110 1232200300041 1.22E-07 2.102 1232200300042 1.29E-07 2.107 1232200300043 1.37E-07 2.092 1232200300044 1.54E-07 2.080 1232200300045 1.69E-07 2.045 1232200300046 ENDDATA 22 0 1232200300047 ENDSUBENT 46 0 1232200399999 SUBENT 12322004 20180523 14411232200400001 BIB 7 11 1232200400002 REACTION (94-PU-239(N,ABS),,ETA) 1232200400003 FACILITY (CHOPF,1USABNL) Brookhaven fast chopper. 1232200400004 SAMPLE 0.033 in. plutonium metal sample was used, which 1232200400005 contained over 90% of 239Pu and about 1% of aluminum. 1232200400006 MONITOR (94-PU-239(N,ABS),,ETA) The data from thermal up to 1232200400007 0.15 eV were obtained with slow chopper and normalized 1232200400008 eta=2.03 at thermal. 1232200400009 ERR-ANALYS (ERR-S) The residual error is statistical. 1232200400010 CORRECTION The corrections for scattering and departure from 1/v 1232200400011 are small (~1%). 1232200400012 STATUS (SCSRS) Also shown in Fig. 4, page 184. 1232200400013 ENDBIB 11 0 1232200400014 COMMON 2 3 1232200400015 EN-NRM MONIT 1232200400016 EV PRT/INC 1232200400017 0.0253 2.03 1232200400018 ENDCOMMON 3 0 1232200400019 DATA 3 28 1232200400020 EN DATA ERR-S 1232200400021 MEV PRT/INC PRT/INC 1232200400022 1.75E-08 2.068 2.2E-02 1232200400023 2.0E-08 2.050 1.5E-02 1232200400024 2.28E-08 2.040 1.0E-02 1232200400025 2.65E-08 2.030 1.0E-02 1232200400026 3.15E-08 1.995 1232200400027 3.75E-08 1.990 1232200400028 4.55E-08 1.940 1232200400029 5.60E-08 1.915 1232200400030 7.30E-08 1.845 1232200400031 8.8E-08 1.798 2.5E-02 1232200400032 9.7E-08 1.748 2.5E-02 1232200400033 9.70E-08 1.768 1232200400034 1.08E-07 1.720 2.2E-02 1232200400035 1.18E-07 1.690 2.2E-02 1232200400036 1.30E-07 1.673 2.0E-02 1232200400037 1.38E-07 1.670 1232200400038 1.45E-07 1.603 2.0E-02 1232200400039 1.60E-07 1.603 2.0E-02 1232200400040 1.80E-07 1.520 2.0E-02 1232200400041 1.98E-07 1.535 1.0E-02 1232200400042 2.06E-07 1.530 2.0E-02 1232200400043 2.33E-07 1.530 2.0E-02 1232200400044 2.63E-07 1.515 2.0E-02 1232200400045 3.40E-07 1.530 2.0E-02 1232200400046 3.75E-07 1.523 2.0E-02 1232200400047 4.50E-07 1.625 2.0E-02 1232200400048 5.48E-07 1.905 3.0E-02 1232200400049 6.80E-07 1.914 3.0E-02 1232200400050 ENDDATA 30 0 1232200400051 ENDSUBENT 50 0 1232200499999 ENDENTRY 4 0 1232299999999