ENTRY 30006 20160929 31753000600000001 SUBENT 30006001 20160929 31753000600100001 BIB 13 46 3000600100002 INSTITUTE (3AULAUA) 3000600100003 REFERENCE (J,JNE,25,321,1971) U-233 nu cfd 2-hump 3000600100004 barrier,Tbl 3000600100005 Full info.previous Nu-bar U-235,Pu-239 cfd theory. 3000600100006 (R,AAEC/TM-574,1971) Same as J.Nucl.En.25,321(1971) 3000600100007 (P,AAEC/PR-33/P,6,1970) Graph of preliminary 3000600100008 results for Pu-239, superseded 3000600100009 (P,INDC(AUL)-8,2,1970) Evaluation of linear slope, 3000600100010 partially superseded 3000600100011 (R,AAEC/E-172,1967) Exp details. The nu, 3000600100012 U233,5+Pu239,41 3000600100013 AUTHOR (R.L.Walsh, J.W.Boldeman) 3000600100014 TITLE The energy dependence of prompt nu-bar for U-233, U-2353000600100015 and Pu-239 below 5.0 MeV. 3000600100016 FACILITY (VDG) 3-MeV Van de Graaff 3000600100017 INC-SOURCE (P-LI7) Li-7(p,n)Be-7 3000600100018 (P-T) T(p,n)He-3 3000600100019 INC-SPECT EN-RSL = Half-width of beam energy spread 3000600100020 METHOD (COINC) Neutron detector was gated to temporary count 3000600100021 store for 40 mu-sec by coincident signals from neutron 3000600100022 and fission counters. After waiting 100 mu-sec, back- 3000600100023 ground was counted for 40 mu-sec. If a second fission 3000600100024 had not occurred in the 180-sec counting cycle, 3000600100025 contents of temporary store were transferred to the 3000600100026 multiple event counter. 3000600100027 DETECTOR (STANK) For neutrons, 240 l. of Gadolinium-loaded3000600100028 trimethylbenzene scintillator (NE323) in a tank viewed 3000600100029 by 12 EMI-9618A photomultipliers arranged in 3 coinci- 3000600100030 dent banks of 4. 3000600100031 (FISCH) Fission counter was a high-speed, 3000600100032 methane-filled double ionization chamber. 3000600100033 The fission chamber was located in the center of a 3000600100034 3-inch axial tube through the tank. The neutron beam 3000600100035 was collimated. 3000600100036 PART-DET (PN) Prompt neutrons 3000600100037 (FF) Fission fragments 3000600100038 MONITOR (98-CF-252(0,F),PR,NU) 3000600100039 assumed as 3.782 3000600100040 ERR-ANALYS Standard error not included in data error 3000600100041 HISTORY (19730117A) Entry revised. U-233 and Pu-239 data 3000600100042 added. 3000600100043 (19761118U) Code correction. YAG. 3000600100044 (20040109A) OS. Data units updated, reference moved to 3000600100045 subentry 1. Dates converted, lower case. 3000600100046 (20160922A) VS. AUTHOR corrected. Coded inf. added in 3000600100047 002-004. COMMON added in 002-003.. 3000600100048 ENDBIB 46 0 3000600100049 COMMON 1 3 3000600100050 MONIT 3000600100051 NO-DIM 3000600100052 3.7820E+00 3000600100053 ENDCOMMON 3 0 3000600100054 ENDSUBENT 53 0 3000600199999 SUBENT 30006002 20160929 31753000600200001 BIB 9 42 3000600200002 REFERENCE (J,JNE,24,191,1970) Full results 3000600200003 (R,AAEC/TM-523,1969) Same as J.Nucl.En. 24,191(1970) 3000600200004 (P,INDC(SEC)-18,10,1971)New expt with 7kev resol 3000600200005 plannd 3000600200006 (P,AAEC/PR-34,8,1971) New expt with 7kev resol 3000600200007 plannd 3000600200008 (P,INDC(AUL)-5,2,1969) Prelim linear fit, superseded 3000600200009 EXP-YEAR (1968) 3000600200010 REACTION (92-U-235(N,F),PR,NU) 3000600200011 SAMPLE (92-U-235,ENR=0.9272) 8.2 mg of uranium with isotopic 3000600200012 composition in percent. U-234=1.28,U-235=92.72, 3000600200013 U-236=0.254,U-238=5.75 3000600200014 CORRECTION Raw data corrected for dead time losses,fission neutron3000600200015 spectra differences (-0.55+-0.22 percent at thermal 3000600200016 energies,up to 0.48+-0.22 percent at 1.9 MeV),energy 3000600200017 degraded neutrons (2.0+-0.5 percent),impurities in the 3000600200018 U235 foil and second neutron group from p-Li7 reaction.3000600200019 Correction for neutron angular distribution negligible.3000600200020 ERR-ANALYS (ERR-T) Standard deviation.Relative accuracy of each 3000600200021 point with respect to the others slightly better than 3000600200022 stated,as all errors include contribution from error in3000600200023 the fission spectra difference correction 3000600200024 (ERR-1) fission neutron spectra differences corr. 0.22%3000600200025 (ERR-2) corr. for energy degraded neutrons 0.5% 3000600200026 - Dead time losses 3000600200027 - Impurities in the U235 foil 3000600200028 - Second neutron group from p-Li7 reaction 3000600200029 COMMENT Linear least squares fit of data gives 3000600200030 NUBAR(E) = (2.412+-0.005) + (0.114+-0.008)E 3000600200031 where E is the neutron energy in MeV. The thermal value3000600200032 (=2.415+-0.008) of Boldeman+Dalton (AAEC/E-172,3/67, 3000600200033 see entry 30046.) has been included in the analysis. 3000600200034 The fit is adequate but see J.Nucl.En.25,321(1971) for 3000600200035 discussion of two-line representation. Data are 3000600200036 compared with other values renormalized to same value 3000600200037 of Cf-252 nu-bar standard given in COMMON. 3000600200038 STATUS (TABLE) Data from J.Nucl.En.24,191(1970),Table 2. 3000600200039 HISTORY (19681118R) Private communication from J.L.Symonds,AUL.3000600200040 (19700921T) Previously DASTAR-00682 3000600200041 (19730116A) Entry revised. Thermal datum omitted. 3000600200042 (20160922A) VS. Coded information added for SAMPLE and 3000600200043 STATUS. ERR-ANALYS modified. COMMON added. 3000600200044 ENDBIB 42 0 3000600200045 COMMON 2 3 3000600200046 ERR-1 ERR-2 3000600200047 PER-CENT PER-CENT 3000600200048 0.22 0.5 3000600200049 ENDCOMMON 3 0 3000600200050 DATA 4 14 3000600200051 EN EN-RSL DATA ERR-T 3000600200052 KEV KEV PRT/FIS PRT/FIS 3000600200053 1.1000E+02 7.0000E+01 2.4170E+00 2.1000E-02 3000600200054 2.2000E+02 3.3000E+01 2.4450E+00 1.5000E-02 3000600200055 3.0000E+02 3.2000E+01 2.4480E+00 1.7000E-02 3000600200056 3.5000E+02 3.2000E+01 2.4560E+00 1.6000E-02 3000600200057 4.0000E+02 3.2000E+01 2.4390E+00 1.6000E-02 3000600200058 4.2500E+02 2.5000E+01 2.4560E+00 1.1000E-02 3000600200059 4.5000E+02 2.9000E+01 2.4560E+00 1.4000E-02 3000600200060 4.8500E+02 2.5000E+01 2.4740E+00 1.0000E-02 3000600200061 5.4000E+02 3.2000E+01 2.4560E+00 1.3000E-02 3000600200062 6.0000E+02 3.2000E+01 2.4760E+00 1.4000E-02 3000600200063 7.0000E+02 3.2000E+01 2.4920E+00 1.4000E-02 3000600200064 1.0000E+03 3.2000E+01 2.5370E+00 1.4000E-02 3000600200065 1.5000E+03 5.0000E+01 2.5890E+00 1.8000E-02 3000600200066 1.9000E+03 5.0000E+01 2.6250E+00 1.6000E-02 3000600200067 ENDDATA 16 0 3000600200068 ENDSUBENT 67 0 3000600299999 SUBENT 30006003 20160929 31753000600300001 BIB 8 48 3000600300002 EXP-YEAR (1970) 3000600300003 REACTION (92-U-233(N,F),PR,NU) 3000600300004 SAMPLE (92-U-233,ENR=0.9927) Isotopic composition (percent) 3000600300005 U-233=99.27,U-234=0.07,U-235=0.04,U-236=0.07,U-238=0.533000600300006 CORRECTION Correction Error in 3000600300007 applied correction 3000600300008 percent percent 3000600300009 1) Statistical accuracy 0.50 3000600300010 2) Fiss. spectr. differences -0.53 to -0.45 0.24 3000600300011 3) Dead time correction 3000600300012 (relative to Cf252 corr) -0.20 0.04 3000600300013 4) Delayed gamma rays 0.00 0.10 3000600300014 5) Thermal contamination +0.12 0.03 3000600300015 6) Second neutron group 3000600300016 from Li7(p,n)Be7 +0.06 0.01 3000600300017 7) Preferential detection 3000600300018 of fragments +0.05 0.05 3000600300019 8) Fragment anisotropy 0.00 0.00 3000600300020 9) False gates +0.05 0.02 3000600300021 10) Impurities in U233 sample 0.00 0.00 3000600300022 11) Electronics errors 0.00 0.03 3000600300023 Items 1),3),5),9) are averages over all runs. 3000600300024 Item 6) is the average for 700 and 917 keV results. 3000600300025 ERR-ANALYS (ERR-T) Total uncertainty determined from the following3000600300026 partial uncertainties: 3000600300027 (ERR-S) Statistical accuracy - 0.50% 3000600300028 (ERR-1) Fiss spect differences - 0.22% 3000600300029 (ERR-2) Dead time correction - 0.04% 3000600300030 (ERR-3) Delayed gamma rays - 0.10% 3000600300031 (ERR-4) Thermal contamination - 0.03% 3000600300032 (ERR-5) Second neutron group from Li7(p,n)Be7 - 0.01% 3000600300033 (ERR-6) Preferential detection of fragments - 0.05% 3000600300034 (ERR-7) False gates - 0.02% 3000600300035 (ERR-8) Electronics errors - 0.03% 3000600300036 COMMENT Linear fit of data was poor. Best two-line fit (minimum3000600300037 composite chi-squared)gives for neutron energy E in MeV3000600300038 Nubar(E) = 2.491 + 0.035E for E less than 0.44 MeV3000600300039 Nubar(E) = 2.453 + 0.122E for E greater than 0.44 MeV3000600300040 These lines intersect at 440 keV. The thermal value 3000600300041 (=2.491+-0.008) of Boldeman+Dalton (AAEC/E-172,3/67, 3000600300042 see entry 30046.) has been included in the analysis. 3000600300043 Similar analyses for U-235 and Pu-239 are discussed 3000600300044 relative to the double-humped fission barrier in 3000600300045 J.Nucl.En.25,321(1971). 3000600300046 STATUS (TABLE) Data from J.Nucl.En.25,321(1971) Table 3. 3000600300047 HISTORY (19720124C) 3000600300048 (20160922A) VS. Coded information added for SAMPLE and 3000600300049 STATUS. ERR-ANALYS modified. COMMON added. 3000600300050 ENDBIB 48 0 3000600300051 COMMON 9 6 3000600300052 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 3000600300053 ERR-6 ERR-7 ERR-8 3000600300054 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3000600300055 PER-CENT PER-CENT PER-CENT 3000600300056 0.50 0.22 0.04 0.10 0.03 0.01 3000600300057 0.05 0.02 0.03 3000600300058 ENDCOMMON 6 0 3000600300059 DATA 4 7 3000600300060 EN EN-RSL DATA ERR-T 3000600300061 KEV KEV PRT/FIS PRT/FIS 3000600300062 3.0000E+02 2.5000E+01 2.5020E+00 1.4000E-02 3000600300063 4.8500E+02 3.1000E+01 2.5080E+00 1.0000E-02 3000600300064 6.0000E+02 3.2000E+01 2.5460E+00 1.2000E-02 3000600300065 7.0000E+02 2.5000E+01 2.5460E+00 1.1000E-02 3000600300066 9.1700E+02 3.3000E+01 2.5640E+00 1.2000E-02 3000600300067 1.5000E+03 5.0000E+01 2.6450E+00 1.9000E-02 3000600300068 1.8700E+03 5.0000E+01 2.6840E+00 2.2000E-02 3000600300069 ENDDATA 9 0 3000600300070 ENDSUBENT 69 0 3000600399999 SUBENT 30006004 20160929 31753000600400001 BIB 6 15 3000600400002 EXP-YEAR (1972) 3000600400003 REACTION (94-PU-239(N,F),PR,NU) 3000600400004 ERR-ANALYS (DATA-ERR) No information on source of uncertainty. 3000600400005 COMMENT Least square fit of experimental data available in 3000600400006 1971 including the preliminary data of the authors 3000600400007 and the thermal value of Boldeman + Dalton AAEC/E-172 3000600400008 (1967) results in 3000600400009 Nubar(E) =(2.889+-0.007) + (0.108+-0.014)*E for 3000600400010 E less than 0.64 MeV 3000600400011 Nubar(E) =(2.861+-0.006) + (0.152+-0.003)*E for 3000600400012 E greater than 0.64 MeV and less than 5.0 MeV. 3000600400013 STATUS (TABLE) Final data from Priv.Com. Walsh 6/72 3000600400014 HISTORY (19730117C) 3000600400015 (20160922U) VS. Coded information added for STATUS 3000600400016 AND ERR-ANALYS. 3000600400017 ENDBIB 15 0 3000600400018 NOCOMMON 0 0 3000600400019 DATA 4 8 3000600400020 EN EN-RSL DATA DATA-ERR 3000600400021 KEV KEV PRT/FIS PRT/FIS 3000600400022 2.0000E+02 5.5000E+01 2.8930E+00 1.3000E-02 3000600400023 3.5000E+02 5.2000E+01 2.9140E+00 1.7000E-02 3000600400024 5.5000E+02 3.6000E+01 2.9380E+00 1.7000E-02 3000600400025 7.0000E+02 3.6000E+01 2.9600E+00 1.7000E-02 3000600400026 9.0000E+02 4.8000E+01 2.9840E+00 1.4000E-02 3000600400027 1.3000E+03 5.0000E+01 3.0220E+00 2.0000E-02 3000600400028 1.6000E+03 5.0000E+01 3.0760E+00 2.1000E-02 3000600400029 1.9000E+03 5.0000E+01 3.1500E+00 1.9000E-02 3000600400030 ENDDATA 10 0 3000600400031 ENDSUBENT 30 0 3000600499999 ENDENTRY 4 0 3000699999999