ENTRY 21494 20230516 2149400000001 SUBENT 21494001 20230516 20231011 2149400100001 BIB 12 81 2149400100002 TITLE Measurements of the fission cross sections of 2149400100003 Pu-239 and Pu-241 relative to that of U-235 in 2149400100004 the neutron energy range 0.016 to 0.55 eV 2149400100005 AUTHOR (P.H.White,J.M.A.Reichelt,G.P.Warner) 2149400100006 INSTITUTE (2UK ALD) 2149400100007 REFERENCE (C,66PARIS,2,29,1966) 2149400100008 FACILITY (REAC,2UK ALD) HERALD Reactor at ALDERMASTON, for 2149400100009 all the measurements. In addition for the 2149400100010 measurements with monoenergetic neutrons 2149400100011 (SPECC,2UK ALD) A crystal spectrometer with an 2149400100012 Al crystal, using the 111-plane, and 2149400100013 (SELVE,2UK ALD) 3 disc mechanical velocity selector in 2149400100014 order to attenuate the 2nd and 3d order neutrons 2149400100015 from the crystal spectrometer. The separation of 2149400100016 the disks was 40 cm, the thickness of the Cd on each 2149400100017 disc 0.05 cm, the number of slits on each disc 50. 2149400100018 The angular velocity was stable within 0.5%. 2149400100019 More details in table 1 of 66PARIS,2,29,1966. 2149400100020 INC-SOURCE (REAC) For the mono-energetic measurements, and a 2149400100021 (THCOL) For the measurements with a Maxwellian 2149400100022 incoming neutron spectrum. One measurement was done 2149400100023 within the graphite thermal column (temp of the 2149400100024 Maxwellian 30+-7 deg C), another one was done with an 2149400100025 external beam (temp of the Maxwellian 90+-10 deg C) 2149400100026 SAMPLE Fission foil isotopic compositions, etc.: 2149400100027 -------------------------------------------------------2149400100028 Coun-! Nuc- ! Mass Number ! Thick-!Assay!Foil2149400100029 ter ! lide ! 234 235 236 238 ! ness !error!th.*2149400100030 ! mg/cm2! % ! % 2149400100031 -------------------------------------------------------2149400100032 1.2 U-235 1.19 92.95 0.18 5.68 0.5 1.0 5.9 2149400100033 2.7 U-235 0.11 99.33 0.25 0.31 0.5 1.0 5.7 2149400100034 -------------------------------------------------------2149400100035 239 240 241 242 2149400100036 -------------------------------------------------------2149400100037 6.7 Pu-239 99.985 0.012 0.003 - 0.2 0.5 3.2 2149400100038 6.12 Pu-239 99.985 0.012 0.003 - 0.06 0.5 0.7 2149400100039 241.1 Pu-241 5.12 5.53 88.95 0.40 0.25 2.0 3.0 2149400100040 241.2 Pu-241 5.12 5.53 88.95 0.40 0.08 2.0 1.1 2149400100041 -------------------------------------------------------2149400100042 * Foil thickness correction (%) 2149400100043 DETECTOR (FISCH) Fission chambers, described in REL-REF. 2149400100044 2*PI geometry, back-to-back foils Pu-239 or 2149400100045 Pu-241 and U-235. 2149400100046 REL-REF (M,21190001,P.H.White,J,JNE/AB,19,325,1965) 2149400100047 (M,21463001,P.H.White,C,65SALZBURG,1,219,1965) 2149400100048 (M,20584001,J.L.Perkin+,J,JNE/AB,19,423,1965) 2149400100049 CORRECTION The measurements with monoenergetic neutrons were 2149400100050 corrected for the stray neutron flux in the reactor 2149400100051 hall (0.3-3.0% of the fission rate), higher order 2149400100052 (than 3) in the spectrometer, incoherent scattering 2149400100053 by the Al-crystal of the scatterer (determined with 2149400100054 the rocking curve). The measurements with the incoming2149400100055 Maxwellian spectra had negligible backgrounds (less 2149400100056 than 0.1%) 2149400100057 ERR-ANALYS (ERR-T) A complete error analysis is given in 2149400100058 Table IV of main reference. 2149400100059 (ERR-1) Error due to isotopic composition 2149400100060 (ERR-2) Error due to fourth and higher order neutrons 2149400100061 (ERR-3) Error due to incoherent background from 2149400100062 crystal spectrometer 2149400100063 (ERR-5) Error of weighing and assay of the plutonium 2149400100064 sample foil 2149400100065 (ERR-6) Error due to fission fragment absorption in 2149400100066 plutonium sample foil 2149400100067 (ERR-7) Error due to extrapolation of fission fragment2149400100068 spectra to zero pulse height for plutonium 2149400100069 (ERR-11) Error of weighing and assay of the uranium 2149400100070 sample foil 2149400100071 (ERR-12) Error due to fission fragment absorption in 2149400100072 uranium sample foil 2149400100073 (ERR-13) Error due to extrapolation of fission fragment2149400100074 spectra to zero pulse height for uranium 2149400100075 HISTORY (19800327T) G.C. From NDD 2149400100076 (20070926A) Date, units and headings corrected. 2149400100077 (20070928U) Last corrections have been done. 2149400100078 Error structure from Table IV of main reference given 2149400100079 (20160907A) SD: Values with FLAG=1 moved to another 2149400100080 Subents (details in Subents 002-007). BIB update. 2149400100081 (20211225A) SD: Corrections in Subents 004, 010, 011. 2149400100082 (20230516A) SD: Corrections in Subents 002, 009. 2149400100083 ENDBIB 81 0 2149400100084 COMMON 3 3 2149400100085 ERR-1 ERR-2 ERR-3 2149400100086 PER-CENT PER-CENT PER-CENT 2149400100087 0.1 0.2 0.3 2149400100088 ENDCOMMON 3 0 2149400100089 ENDSUBENT 88 0 2149400199999 SUBENT 21494002 20230516 20231011 2149400200001 BIB 5 17 2149400200002 REACTION ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2149400200003 2200 m/sec value. 2149400200004 ERR-ANALYS (ERR-8) Error due to the hardening of neutron spectrum2149400200005 by captive in hardening materials 2149400200006 (ERR-9) Error due to beam non-uniformity 2149400200007 (ERR-10) Error due to uncertainty of neutron spectrum 2149400200008 (ERR-S) Statistical error 2149400200009 FLAG (2.) Data from measurement with extracted beam of 2149400200010 the thermal column. 2149400200011 (3.) Data from measurement within the thermal 2149400200012 column. 2149400200013 STATUS (TABLE,,P.H.White+,C,66PARIS,2,29,1966) Tbl. V 2149400200014 HISTORY (19800327T) G.C. 2149400200015 (20070926A) RATIO -> DATA, ARB-UNITS -> NO-DIM, EN-RSL 2149400200016 and FLAG columns moved to col. 3,4. 2149400200017 (20160907A) SD: Value with FLAG=1 moved to Subent 006. 2149400200018 (20230516A) SD: ERR-T deleted from COMMON section. 2149400200019 ENDBIB 17 0 2149400200020 COMMON 11 6 2149400200021 EN ERR-5 ERR-6 ERR-7 ERR-8 ERR-9 2149400200022 ERR-10 ERR-11 ERR-12 ERR-13 ERR-S 2149400200023 EV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149400200024 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149400200025 0.0253 0.5 0.4 0.4 0.1 0.12149400200026 1.0 0.5 0.5 1. 0.5 2149400200027 ENDCOMMON 6 0 2149400200028 DATA 3 2 2149400200029 DATA ERR-T FLAG 2149400200030 NO-DIM NO-DIM NO-DIM 2149400200031 1.235 0.022 2. 2149400200032 1.277 0.025 3. 2149400200033 ENDDATA 4 0 2149400200034 ENDSUBENT 33 0 2149400299999 SUBENT 21494003 20160907 22522149400300001 BIB 5 19 2149400300002 REACTION ((94-PU-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2149400300003 2200 m/sec value. 2149400300004 ERR-ANALYS (ERR-8) Error due to the hardening of neutron spectrum2149400300005 by captive in hardening materials 2149400300006 (ERR-9) Error due to beam non-uniformity 2149400300007 (ERR-10) Error due to uncertainty of neutron spectrum 2149400300008 (ERR-14) Error due to decay of Pu-241 sample since its 2149400300009 separation from Am-241 2149400300010 (ERR-S) Statistical error 2149400300011 FLAG (2.) Data from measurement with extracted beam of 2149400300012 the thermal column. 2149400300013 (3.) Data from measurement within the thermal 2149400300014 column. 2149400300015 STATUS (TABLE) Tbl. V of 66PARIS,2,29,1966 2149400300016 HISTORY (19800327T) G.C. 2149400300017 (20070926A) "RATIO" TO "DATA" , "ARB-UNITS" to 2149400300018 "NO-DIM" changed, "EN-RSL" AND "FLAG" columns 2149400300019 moved to col. 3,4 2149400300020 (20160907A) SD: Value with FLAG=1 moved to Subent 007. 2149400300021 ENDBIB 19 0 2149400300022 COMMON 13 9 2149400300023 EN ERR-5 ERR-6 ERR-7 ERR-8 ERR-9 2149400300024 ERR-10 ERR-11 ERR-12 ERR-13 ERR-14 ERR-T 2149400300025 ERR-S 2149400300026 EV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149400300027 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT NO-DIM 2149400300028 PER-CENT 2149400300029 0.0253 2.0 0.4 0.4 0.1 0.1 2149400300030 1.0 0.5 0.5 1. 0.1 0.048 2149400300031 0.5 2149400300032 ENDCOMMON 9 0 2149400300033 DATA 2 2 2149400300034 DATA FLAG 2149400300035 NO-DIM NO-DIM 2149400300036 1.722 2. 2149400300037 1.782 3. 2149400300038 ENDDATA 4 0 2149400300039 ENDSUBENT 38 0 2149400399999 SUBENT 21494004 20211225 23062149400400001 BIB 7 20 2149400400002 REACTION (94-PU-239(N,F),,SIG) 2200 m/sec value. 2149400400003 MONITOR (92-U-235(N,F),,SIG) 2200 m/sec value 2149400400004 INC-SOURCE Neutrons from or within thermal column 2149400400005 ERR-ANALYS (ERR-8) Error due to the hardening of neutron spectrum2149400400006 by captive in hardening materials 2149400400007 (ERR-9) Error due to beam non-uniformity 2149400400008 (ERR-10) Error due to uncertainty of neutron spectrum 2149400400009 (ERR-S) Statistical error 2149400400010 FLAG (2.) Data from measurement with extracted beam of 2149400400011 the thermal column. 2149400400012 (3.) Data from measurement within the thermal 2149400400013 column. 2149400400014 STATUS (TABLE) Tbl. V of 66PARIS,2,29,1966 2149400400015 (COREL,21494010) data meausred with 2149400400016 neutrons from crystal spectrometer 2149400400017 HISTORY (19800327T) G.C. 2149400400018 (20070928U) Last checking has been done. 2149400400019 (20160907A) SD: Value of cross section from the 2149400400020 monoenergetic neutron source moved to Subent 010. 2149400400021 (20211225U) SD:Small correction in prev. history string2149400400022 ENDBIB 20 0 2149400400023 COMMON 12 6 2149400400024 EN MONIT ERR-5 ERR-6 ERR-7 ERR-8 2149400400025 ERR-9 ERR-10 ERR-11 ERR-12 ERR-13 ERR-S 2149400400026 EV B PER-CENT PER-CENT PER-CENT PER-CENT 2149400400027 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149400400028 0.0253 577. 0.5 0.4 0.4 0.1 2149400400029 0.1 1.0 0.5 0.5 1. 0.5 2149400400030 ENDCOMMON 6 0 2149400400031 DATA 3 2 2149400400032 DATA ERR-T FLAG 2149400400033 B B NO-DIM 2149400400034 713. 15. 2. 2149400400035 737. 17. 3. 2149400400036 ENDDATA 4 0 2149400400037 ENDSUBENT 36 0 2149400499999 SUBENT 21494005 20160907 22522149400500001 BIB 7 20 2149400500002 REACTION (94-PU-241(N,F),,SIG) 2200 m/sec value. 2149400500003 MONITOR (92-U-235(N,F),,SIG) 2200 m/sec value 577 b. 2149400500004 COMMENT Deduced from thermal measurements 2149400500005 ERR-ANALYS (ERR-8) Error due to the hardening of neutron spectrum2149400500006 by captive in hardening materials 2149400500007 (ERR-9) Error due to beam non-uniformity 2149400500008 (ERR-10) Error due to uncertainty of neutron spectrum 2149400500009 (ERR-14) Error due to decay of Pu-241 sample since its 2149400500010 separation from Am-241 2149400500011 (ERR-S) Statistical error 2149400500012 FLAG (2.) Data from measurement with extracted beam of 2149400500013 the thermal column. 2149400500014 (3.) Data from measurement within the thermal 2149400500015 column. 2149400500016 STATUS (TABLE) Tbl. V of 66PARIS,2,29,1966 2149400500017 HISTORY (19800327T) G.C. 2149400500018 (20070926U) Columns "EN-RSL" AND "FLAG"- moved to 2149400500019 cols 3,4 2149400500020 (20160907A) SD: Value of cross section from the 2149400500021 monoenergetic neutron source moved to Subent 011. 2149400500022 ENDBIB 20 0 2149400500023 COMMON 15 9 2149400500024 EN MONIT ERR-5 ERR-6 ERR-7 ERR-8 2149400500025 ERR-9 ERR-10 ERR-11 ERR-12 ERR-13 ERR-14 2149400500026 ERR-T ERR-T ERR-S 2149400500027 EV B PER-CENT PER-CENT PER-CENT PER-CENT 2149400500028 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149400500029 PER-CENT PER-CENT PER-CENT 2149400500030 0.0253 577. 2.0 0.4 0.4 0.1 2149400500031 0.1 1.0 0.5 0.5 1. 0.1 2149400500032 2.7 29. 0.5 2149400500033 ENDCOMMON 9 0 2149400500034 DATA 2 2 2149400500035 DATA FLAG 2149400500036 B NO-DIM 2149400500037 994. 2. 2149400500038 1028. 3. 2149400500039 ENDDATA 4 0 2149400500040 ENDSUBENT 39 0 2149400599999 SUBENT 21494006 20160907 22522149400600001 BIB 5 10 2149400600002 REACTION ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2149400600003 COMMENT The energy resolution function is asymmetric. 2149400600004 ERR-ANALYS (ERR-4) Error due to neutron beam non-uniformity 2149400600005 (ERR-S) Statistical error 2149400600006 STATUS (TABLE) Tbl. VI of 66PARIS,2,29,1966 2149400600007 HISTORY (19800327T) G.C. 2149400600008 (20070926A) "RATIO" TO "DATA" , "ARB-UNITS" to 2149400600009 "NO-DIM" changed. Error structure given. 2149400600010 (20160907A) SD: Two values added from Subents 002,004. 2149400600011 Values of ERR-T in % deleted (duplication excluded). 2149400600012 ENDBIB 10 0 2149400600013 COMMON 7 6 2149400600014 ERR-4 ERR-5 ERR-6 ERR-7 ERR-11 ERR-12 2149400600015 ERR-13 2149400600016 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149400600017 PER-CENT 2149400600018 0.5 0.4 0.4 1.0 0.5 0.52149400600019 1. 2149400600020 ENDCOMMON 6 0 2149400600021 DATA 6 8 2149400600022 EN EN-RSL EN-ERR DATA ERR-T ERR-S 2149400600023 EV PER-CENT MILLI-EV NO-DIM NO-DIM PER-CENT 2149400600024 0.016 1.0 0.04 1.208 0.022 0.52149400600025 0.0253 1.4 1.253 0.022 0.52149400600026 0.0253 1.4 723. 15. 0.52149400600027 0.051 4.0 0.5 1.374 0.024 0.52149400600028 0.117 6.6 2. 2.010 0.036 0.52149400600029 0.161 7.8 3. 2.93 0.05 0.52149400600030 0.270 10.2 7. 12.51 0.3 0.52149400600031 0.545 14.4 20. 1.94 0.05 1.02149400600032 ENDDATA 10 0 2149400600033 ENDSUBENT 32 0 2149400699999 SUBENT 21494007 20160907 22522149400700001 BIB 5 12 2149400700002 REACTION ((94-PU-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2149400700003 COMMENT .The energy resolution function is asymmetric. 2149400700004 ERR-ANALYS (ERR-4) Error due to neutron beam non-uniformity 2149400700005 (ERR-14) Error due to decay of Pu-241 sample since its 2149400700006 separation from Am-241 2149400700007 (ERR-S) Statistical error 2149400700008 STATUS (TABLE) Tbl. VI of 66PARIS,2,29,1966 2149400700009 HISTORY (19800327T) G.C. 2149400700010 (20070926A) "RATIO" TO "DATA" , "ARB-UNITS" to 2149400700011 "NO-DIM" changed. Error structure given 2149400700012 (20160907A) SD: Two values added from Subents 003,005. 2149400700013 Values of ERR-T in % deleted (duplication excluded). 2149400700014 ENDBIB 12 0 2149400700015 COMMON 8 6 2149400700016 ERR-4 ERR-5 ERR-6 ERR-7 ERR-11 ERR-12 2149400700017 ERR-13 ERR-14 2149400700018 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149400700019 PER-CENT PER-CENT 2149400700020 1. 2.0 0.4 0.4 1.0 0.52149400700021 0.5 0.1 2149400700022 ENDCOMMON 6 0 2149400700023 DATA 6 8 2149400700024 EN EN-RSL EN-ERR DATA ERR-T ERR-S 2149400700025 EV PER-CENT MILLI-EV NO-DIM NO-DIM PER-CENT 2149400700026 0.016 1.0 0.04 1.681 0.044 0.52149400700027 0.0253 1.4 1.772 0.048 0.52149400700028 0.0253 1.4 1022. 29. 0.52149400700029 0.051 4.0 0.5 1.876 0.05 0.52149400700030 0.117 6.6 2. 2.719 0.07 0.52149400700031 0.161 7.8 3. 3.96 0.10 0.52149400700032 0.270 10.2 7. 8.23 0.3 0.52149400700033 0.545 14.4 20. 0.806 0.02 1.02149400700034 ENDDATA 10 0 2149400700035 ENDSUBENT 34 0 2149400799999 SUBENT 21494008 20160907 22522149400800001 BIB 5 12 2149400800002 REACTION ((94-PU-239(N,F),,SIG,,MXW)/ 2149400800003 (92-U-235(N,F),,SIG,,MXW)) At 30. And 90. Degr. C. 2149400800004 ERR-ANALYS (ERR-8) Error due to the hardening of neutron spectrum2149400800005 by captive in hardening materials 2149400800006 (ERR-9) Error due to beam non-uniformity 2149400800007 (ERR-10) Error due to uncertainty of neutron spectrum 2149400800008 INC-SPECT Reactions induced by extracted beam neutrons 2149400800009 and by neutrons inside a thermal column. 2149400800010 STATUS (TABLE) Tbl. V of 66PARIS,2,29,1966 2149400800011 HISTORY (19800328T) G.C. 2149400800012 (20070926A) "RATIO" TO "DATA" , "ARB-UNITS" to 2149400800013 "NO-DIM" changed 2149400800014 ENDBIB 12 0 2149400800015 COMMON 11 6 2149400800016 ERR-5 ERR-6 ERR-7 ERR-8 ERR-9 ERR-10 2149400800017 ERR-11 ERR-12 ERR-13 ERR-T ERR-T 2149400800018 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149400800019 PER-CENT PER-CENT PER-CENT NO-DIM PER-CENT 2149400800020 0.5 0.4 0.4 0.1 0.1 1.0 2149400800021 1.0 0.5 0.5 0.02 1.8 2149400800022 ENDCOMMON 6 0 2149400800023 DATA 2 2 2149400800024 EN-DUMMY DATA 2149400800025 EV NO-DIM 2149400800026 0.0253 1.385 2149400800027 0.0313 1.405 2149400800028 ENDDATA 4 0 2149400800029 ENDSUBENT 28 0 2149400899999 SUBENT 21494009 20230516 20231011 2149400900001 BIB 5 15 2149400900002 REACTION ((94-PU-241(N,F),,SIG,,MXW)/ 2149400900003 (92-U-235(N,F),,SIG,,MXW)) At 30. And 90. Degr C. 2149400900004 INC-SPECT Reactions induced by neutrons of an extracted 2149400900005 beam (90 degr. C) and by neutrons inside a thermal 2149400900006 column (30 deg. C) 2149400900007 ERR-ANALYS (ERR-8) Error due to the hardening of neutron spectrum2149400900008 by captive in hardening materials 2149400900009 (ERR-9) Error due to beam non-uniformity 2149400900010 (ERR-10) Error due to uncertainty of neutron spectrum 2149400900011 (ERR-14) Error due to decay of Pu-241 sample since its 2149400900012 separation from Am-241 2149400900013 STATUS (TABLE,,P.H.White+,C,66PARIS,2,29,1966) Tbl. V 2149400900014 HISTORY (19800328T) G.C. 2149400900015 (20070926A) RATIO -> DATA, ARB-UNITS -> NO-DIM. 2149400900016 (20230516A) SD: ERR-T deleted from COMMON section. 2149400900017 ENDBIB 15 0 2149400900018 COMMON 10 6 2149400900019 ERR-5 ERR-6 ERR-7 ERR-8 ERR-9 ERR-10 2149400900020 ERR-11 ERR-12 ERR-13 ERR-14 2149400900021 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149400900022 PER-CENT PER-CENT PER-CENT PER-CENT 2149400900023 2.0 0.4 0.4 0.1 0.1 1.02149400900024 1.0 0.5 0.5 0.1 2149400900025 ENDCOMMON 6 0 2149400900026 DATA 3 2 2149400900027 EN-DUMMY DATA ERR-T 2149400900028 EV NO-DIM NO-DIM 2149400900029 0.0253 1.920 0.047 2149400900030 0.0313 1.966 0.048 2149400900031 ENDDATA 4 0 2149400900032 ENDSUBENT 31 0 2149400999999 SUBENT 21494010 20211225 23062149401000001 BIB 6 13 2149401000002 REACTION (94-PU-239(N,F),,SIG) 2200 m/sec value. 2149401000003 MONITOR (92-U-235(N,F),,SIG) 2200 m/sec value 2149401000004 INC-SOURCE Monoenergetic neutron source 2149401000005 ERR-ANALYS (ERR-8) Error due to the hardening of neutron spectrum2149401000006 by captive in hardening materials 2149401000007 (ERR-9) Error due to beam non-uniformity 2149401000008 (ERR-10) Error due to uncertainty of neutron spectrum 2149401000009 (ERR-S) Statistical error 2149401000010 STATUS (TABLE) Tbl. V of 66PARIS,2,29,1966 2149401000011 (COREL,21494004) data meausred with 2149401000012 neutrons from thermal column 2149401000013 HISTORY (20160907T) SD: Part of Subent 004. 2149401000014 (20211225U) SD:Small correction in prev. history string2149401000015 ENDBIB 13 0 2149401000016 COMMON 11 6 2149401000017 MONIT ERR-5 ERR-6 ERR-7 ERR-8 ERR-9 2149401000018 ERR-10 ERR-11 ERR-12 ERR-13 ERR-S 2149401000019 B PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149401000020 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149401000021 577. 0.5 0.4 0.4 0.1 0.12149401000022 1.0 0.5 0.5 1. 0.5 2149401000023 ENDCOMMON 6 0 2149401000024 DATA 3 1 2149401000025 EN DATA ERR-T 2149401000026 EV B B 2149401000027 0.0253 723. 15. 2149401000028 ENDDATA 3 0 2149401000029 ENDSUBENT 28 0 2149401099999 SUBENT 21494011 20211225 23062149401100001 BIB 6 14 2149401100002 REACTION (94-PU-241(N,F),,SIG) 2200 m/sec value. 2149401100003 MONITOR (92-U-235(N,F),,SIG) 2200 m/sec value 577 b. 2149401100004 INC-SOURCE Monoenergetic neutron source 2149401100005 ERR-ANALYS (ERR-8) Error due to the hardening of neutron spectrum2149401100006 by captive in hardening materials 2149401100007 (ERR-9) Error due to beam non-uniformity 2149401100008 (ERR-10) Error due to uncertainty of neutron spectrum 2149401100009 (ERR-14) Error due to decay of Pu-241 sample since its 2149401100010 separation from Am-241 2149401100011 (ERR-S) Statistical error 2149401100012 STATUS (TABLE) Tbl. V of 66PARIS,2,29,1966 2149401100013 HISTORY (20160907T) SD: Part of Subent 005. 2149401100014 (20211225A) SD:Small correction in prev. history string2149401100015 Energy and total error repeated in COMMON deleted. 2149401100016 ENDBIB 14 0 2149401100017 COMMON 12 6 2149401100018 MONIT ERR-5 ERR-6 ERR-7 ERR-8 ERR-9 2149401100019 ERR-10 ERR-11 ERR-12 ERR-13 ERR-14 ERR-S 2149401100020 B PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149401100021 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2149401100022 577. 2.0 0.4 0.4 0.1 0.12149401100023 1.0 0.5 0.5 1. 0.1 0.52149401100024 ENDCOMMON 6 0 2149401100025 DATA 3 1 2149401100026 EN DATA ERR-T 2149401100027 EV B B 2149401100028 0.0253 1022. 29. 2149401100029 ENDDATA 3 0 2149401100030 ENDSUBENT 29 0 2149401199999 ENDENTRY 11 0 2149499999999