ENTRY 30367 20130625 31603036700000001 SUBENT 30367001 20130625 31603036700100001 BIB 11 29 3036700100002 TITLE Relative nu-bar measurements for Cm-248, Pu-240 and 3036700100003 Pu-242 3036700100004 AUTHOR (J.W.Boldeman) 3036700100005 INSTITUTE (3AULAUA) 3036700100006 REFERENCE (C,73KIEV,4,114,1973) Revised data given 3036700100007 (J,JNE,22,63,1968) Data for Pu-240, 242 (X4 30047) 3036700100008 REL-REF (I,,R.L.Walsh,R,AAEC/E-172,196703) 3036700100009 Details of NE-323 liquid scintillator 3036700100010 METHOD Nu-bar measurement relative to nu-bar(prompt) in the 3036700100011 spontaneous fission of Cf-252 using a large liquid 3036700100012 scintillator as the neutron detector. 3036700100013 DETECTOR (STANK) NE-323 liquid scintillator tank containing 3036700100014 gadolinium loaded liquid scintillator. 3036700100015 MONITOR (98-CF-252(0,F),PR,NU) 3036700100016 PART-DET (N) Prompt neutrons. 3036700100017 CORRECTION The correction caused by difference in the source 3036700100018 fission neutron spectrum and that of the Cf-252 3036700100019 standard has been estimated using the experimentally 3036700100020 confirmed efficiency versus neutron energy curve 3036700100021 (see Boldeman, 2nd Nat.Soviet Conf. on Neutron Phys., 3036700100022 Kiev,May 1973,Vol.4 p.83) and assuming that the 3036700100023 fission neutron spectra are accurately represented by 3036700100024 a Maxwellian distribution with assumed temperature as 3036700100025 the following: 3036700100026 kT=1.433+/-0.03 (Cf-252), 1.362+/-0.03 (Cm-248), 3036700100027 1.19+/-0.03 (Pu-240), 1.207+/-0.07 (Pu-242). 3036700100028 HISTORY (19770118C) KO. 3036700100029 (20090115A) BIB section updated, 3 subentries added 3036700100030 (20130625U) On. REFERENCE: AAEC/E moved to REL-REF 3036700100031 ENDBIB 29 0 3036700100032 COMMON 1 3 3036700100033 MONIT 3036700100034 PRT/FIS 3036700100035 3.724 3036700100036 ENDCOMMON 3 0 3036700100037 ENDSUBENT 36 0 3036700199999 SUBENT 30367002 20090104 31343036700200001 BIB 5 19 3036700200002 REACTION (96-CM-248(0,F),PR,NU) 3036700200003 SAMPLE Isotopic analysis of curium-244 source is, (in %) 3036700200004 Cm-244 0.006, Cm-245 0.050, Cm-246 3.110, 3036700200005 Cm-247 0.014, Cm-248 96.820. 3036700200006 COMMENT Determined also neutron emission probabilities, 3036700200007 see subentry 5. 3036700200008 Second moment of nu about origin = 10.928+-0.041, 3036700200009 second moment about nu-bar = 1.368+-0.005. 3036700200010 STATUS (TABLE) Data from Table 2 of 2nd Nat.Soviet Conf.on 3036700200011 Neutron Physics,Kiev May 1973, Vol 4,p.114. 3036700200012 ERR-ANALYS (ERR-T) Total error is given. 3036700200013 Percentage corrections applied to experimental value 3036700200014 and percentage contributions to nu-bar error are: 3036700200015 Correction Contrib.to error3036700200016 1.Statist.Accuracy 0.155 3036700200017 2.Bg fiss.Correction +0.07 0.01 3036700200018 3.Fiss.Spec.Difference -0.23 0.14 3036700200019 4.Dead time correct. +0.20 0.02 3036700200020 5.Delayed gamma-ray 0.00 0.10 3036700200021 ENDBIB 19 0 3036700200022 NOCOMMON 0 0 3036700200023 DATA 2 1 3036700200024 DATA ERR-T 3036700200025 PRT/FIS PRT/FIS 3036700200026 3.0920E+00 7.0000E-03 3036700200027 ENDDATA 3 0 3036700200028 ENDSUBENT 27 0 3036700299999 SUBENT 30367003 20090104 31343036700300001 BIB 4 19 3036700300002 REACTION (94-PU-240(0,F),PR,NU) 3036700300003 Revised value. 3036700300004 COMMENT Determined also neutron emission probabilities,(rev.) 3036700300005 see subentry 6. 3036700300006 Second moment of nu about origin = 5.804+-0.035, 3036700300007 second moment about nu-bar = 0.821+-0.002. 3036700300008 STATUS This entry supersedes EXFOR 30047.002. 3036700300009 value has been revised following the absolute 3036700300010 calibration of the liquid scintillator tank and better 3036700300011 fission delayed gamma ray data. 3036700300012 (TABLE) Revised value from Table 5 of 2nd Nat.Soviet 3036700300013 Conf.on Neutron Physics,Kiev,May 1973, vol 4 p.114. 3036700300014 ERR-ANALYS (ERR-T) Total error is given. 3036700300015 Percentage corrections applied to experimental value 3036700300016 and percentage contributions to nu-bar error are: 3036700300017 Correction Contrib.to error3036700300018 1.Statist.Accuracy 0.16 3036700300019 2.Fiss.Spec.Difference -0.93 0.14 3036700300020 3.Dead time correct. -0.40 0.08 3036700300021 ENDBIB 19 0 3036700300022 NOCOMMON 0 0 3036700300023 DATA 2 1 3036700300024 DATA ERR-T 3036700300025 PRT/FIS PRT/FIS 3036700300026 2.1190E+00 7.0000E-03 3036700300027 ENDDATA 3 0 3036700300028 ENDSUBENT 27 0 3036700399999 SUBENT 30367004 20090104 31343036700400001 BIB 4 19 3036700400002 REACTION (94-PU-242(0,F),PR,NU) 3036700400003 Revised value. 3036700400004 COMMENT Determined also neutron emission probabilities,(rev.), 3036700400005 see subentry 7. 3036700400006 Second moment of nu about origin = 5.758+-0.036, 3036700400007 second moment about nu-bar = 0.821+-0.002. 3036700400008 STATUS This entry supersedes EXFOR 30047.003. The value has 3036700400009 been revised following the absolute calibration of the 3036700400010 liquid scintillator tank and better fission delayed 3036700400011 gamma ray data. 3036700400012 (TABLE) Revised value from Table 5 of 2nd Nat.Soviet 3036700400013 Conf.on Neutron Physics,Kiev,May 1973,vol 4 p.114. 3036700400014 ERR-ANALYS (ERR-T) Total error is given. 3036700400015 Percentage corrections applied to experimental value 3036700400016 and percentage contributions to nu-bar error are: 3036700400017 Correction Contrib.to error3036700400018 1.Statist.Accuracy 0.17 3036700400019 2.Fiss.Spec.Difference -0.87 0.14 3036700400020 3.Dead time correct. -0.40 0.08 3036700400021 ENDBIB 19 0 3036700400022 NOCOMMON 0 0 3036700400023 DATA 2 1 3036700400024 DATA ERR-T 3036700400025 PRT/FIS PRT/FIS 3036700400026 2.1090E+00 7.0000E-03 3036700400027 ENDDATA 3 0 3036700400028 ENDSUBENT 27 0 3036700499999 SUBENT 30367005 20130625 31603036700500001 BIB 4 6 3036700500002 REACTION (96-CM-248(0,F),PR/NUM,NU) 3036700500003 SAMPLE (96-CM-248,ENR=0.96820) 1 ug 3036700500004 STATUS (TABLE) Data from Table 2 of 2nd Nat.Soviet Conf. on 3036700500005 Neutron Physics, Kiev May 1973, Vol 4, p.114. 3036700500006 HISTORY (20090128C) OS. Moved from free text. 3036700500007 (20130625A) On. REACTION: NPART removed, PR added 3036700500008 ENDBIB 6 0 3036700500009 NOCOMMON 0 0 3036700500010 DATA 3 8 3036700500011 PART-OUT DATA DATA-ERR 3036700500012 NO-DIM NO-DIM NO-DIM 3036700500013 0. 0.0071 0.001 3036700500014 1. 0.0671 0.0021 3036700500015 2. 0.2343 0.0031 3036700500016 3. 0.3449 0.0035 3036700500017 4. 0.2372 0.0034 3036700500018 5. 0.0868 0.0040 3036700500019 6. 0.0195 0.0020 3036700500020 7. 0.0031 0.0014 3036700500021 ENDDATA 10 0 3036700500022 ENDSUBENT 21 0 3036700599999 SUBENT 30367006 20130625 31603036700600001 BIB 4 6 3036700600002 REACTION (94-PU-240(0,F),PR/NUM,NU) 3036700600003 SAMPLE (94-PU-240,ENR=0.7414) total weight 800 mg 3036700600004 STATUS (TABLE) Data from Table 5 of 2nd Nat.Soviet Conf. on 3036700600005 Neutron Physics, Kiev May 1973, Vol 4, p.114. 3036700600006 HISTORY (20090128C) OS. Moved from free text. 3036700600007 (20130625A) On. REACTION: NPART removed, PR added 3036700600008 ENDBIB 6 0 3036700600009 NOCOMMON 0 0 3036700600010 DATA 3 7 3036700600011 PART-OUT DATA DATA-ERR 3036700600012 NO-DIM NO-DIM NO-DIM 3036700600013 0. 0.0693 0.010 3036700600014 1. 0.2384 0.0021 3036700600015 2. 0.3319 0.0022 3036700600016 3. 0.2456 0.0028 3036700600017 4. 0.0972 0.0031 3036700600018 5. 0.0151 0.0015 3036700600019 6. 0.0026 0.0005 3036700600020 ENDDATA 9 0 3036700600021 ENDSUBENT 20 0 3036700699999 SUBENT 30367007 20130625 31603036700700001 BIB 4 6 3036700700002 REACTION (94-PU-242(0,F),PR/NUM,NU) 3036700700003 SAMPLE (94-PU-242,ENR=0.9988) total weight 600 mg 3036700700004 STATUS (TABLE) Data from Table 5 of 2nd Nat.Soviet Conf. on 3036700700005 Neutron Physics, Kiev May 1973, Vol 4, p.114. 3036700700006 HISTORY (20090128C) OS. Moved from free text. 3036700700007 (20130625A) On. REACTION: NPART removed, PR added 3036700700008 ENDBIB 6 0 3036700700009 NOCOMMON 0 0 3036700700010 DATA 3 7 3036700700011 PART-OUT DATA DATA-ERR 3036700700012 NO-DIM NO-DIM NO-DIM 3036700700013 0. 0.0693 0.011 3036700700014 1. 0.2381 0.0021 3036700700015 2. 0.3373 0.0024 3036700700016 3. 0.2405 0.0027 3036700700017 4. 0.0958 0.0032 3036700700018 5. 0.0151 0.0015 3036700700019 6. 0.0027 0.0005 3036700700020 ENDDATA 9 0 3036700700021 ENDSUBENT 20 0 3036700799999 ENDENTRY 7 0 3036799999999