ENTRY 40412 20200318 41864041200000001 SUBENT 40412001 20200318 41864041200100001 BIB 13 76 4041200100002 INSTITUTE (4RUSFEI) 4041200100003 REFERENCE (J,AE,38,82,1975) Issue 2. 4041200100004 (J,SJA,38,105,1975) Engl.translation of AE,38,82,1975. 4041200100005 #doi:10.1007/BF01208866 4041200100006 (R,FEI-274,1971) 4041200100007 (R,INDC(CCP)-21,1972) Engl.translation of R,FEI-274. 4041200100008 (C,71KIEV,1,293,1971) Graphs of Alpha value. 4041200100009 (C,71KIEV,1,301,1971) Exp.method. 4041200100010 (R,FEI-290,1972) Facility details. 4041200100011 (J,AE,32,85,1972) Issue 1. Graphs of Alpha value. 4041200100012 (J,SJA,32,95,1972) Engl.translation of AE,32,85,1972 4041200100013 #doi:10.1007/BF01261042 4041200100014 ((R,YK-15,12,1974)= 4041200100015 (R,INDC(CCP)-57,12,1974)) 4041200100016 Even at NDS web-site in this INDC(CCP)-57 pdf these pag4041200100017 are absent. 4041200100018 AUTHOR (V.N.Kononov, E.D.Poletaev,B.D.Yurlov, Yu.S.Prokopets, 4041200100019 A.A.Metlev, Yu.Ya.Stavisskiy) 4041200100020 TITLE Measurement of alpha and the 235U and 239Pu fission and4041200100021 capture cross sections for 10-80 keV neutrons 4041200100022 FACILITY (VDG,4RUSFEI) FEI pulsed Van-de-Graaff accelerator. 4041200100023 Pulse duration 22ns, frequency 300.kHz. 4041200100024 INC-SOURCE (P-LI7) Proton-Lithium-7 4041200100025 Metal lithium targets were used 4041200100026 (P-T) Proton-tritium, standard tritium-titanium 4041200100027 targets were used 4041200100028 SAMPLE Four metal Pu-239 discs of 40 mm diameter, 2.9E-03 4041200100029 nuclei/b thickness. Total weight 14.5 g. 4041200100030 Pu-240 content in the sample - 0.2%. 4041200100031 Triuranium octoxide U3O8 (90.3 percents of U-235) 4041200100032 Sample of 4.1E-3 U-235-nuclei/b thickness in aluminum 4041200100033 shell of 40 mm Diameter and 0.5mm wall thickness. 4041200100034 U3O8 weight - 24.4g. 4041200100035 Background measurements equivalent scattering samples 4041200100036 of carbon and lead were used 4041200100037 METHOD (TOF) Time-of-flight method with resolution 18 4041200100038 nsec/m for neutron energy range from 10 keV to 80 keV 4041200100039 And energy resolution from 10 keV to 30 keV 4041200100040 For neutron energy range from 100 keV to 1 MeV 4041200100041 at working on monoenergetic neutrons. 4041200100042 Flight path 1.18 m. 4041200100043 DETECTOR (STANK) Large (400. l) liquid scintillation detector 4041200100044 loaded with cadmium 4041200100045 (FISCH) Fast ionization chamber with Cf-252. 4041200100046 (NAICR) NaI(Tl) Crystal of 150x80 mm size detector. 4041200100047 Amplitude resolution about 13 % at E-gamma=478 keV, 4041200100048 time resolution 8ns at E-gamma 420.-540. keV. 4041200100049 MONITOR Measurement of the capture-to-fission cross-section 4041200100050 ratios (ALFA) was absolute 4041200100051 The fission cross-sections have been measured using 4041200100052 energy dependence of B-10(n,alpha-gamma) reaction as 4041200100053 given by Sowerby M.G. et al, 70HELSINKI,1,161 and 4041200100054 Macklin P.L. et al, Phys.Rev., 165, 1147, 1968. 4041200100055 Normalization of fission cross-section was made over 4041200100056 energy region 30-40 keV to evaluated data by Sowerby 4041200100057 et al, Ann. Of Sci. and Eng., V1,No.718,1974. 4041200100058 CORRECTION Correction for isotopic impurities,correction for 4041200100059 neutron multiplication in the samples, correction for 4041200100060 energy dependence nu-bar, correction for multiple 4041200100061 neutron scattering and resonance self-shielding. 4041200100062 STATUS (APRVD) Data in ENTRIES 40073 and 40300 are 4041200100063 superseded by author's revision and revised data 4041200100064 entered in this ENTRY 4041200100065 HISTORY (19770110C) 4041200100066 (19791211U) 4041200100067 (19840227U) Reaction formalism introduced 4041200100068 (20070924A) M.M.Dates were corrected for 4-digits year.4041200100069 BIB information was added. 4041200100070 (20140325U) Ref. J,SJA,38,105,1975 was added. 4041200100071 Minor corrections of BIB information. 4041200100072 AV was added in SF8 in Subents 003-004,006-008. 4041200100073 (20191209A) Correction of ERR-ANALYS in Subents 4041200100074 003,004,006,007 4041200100075 (20200318U) ref. R,INDC(CCP)-57,12,1974 was added, even4041200100076 at NDS web-site in this INDC(CCP)-57 pdf these pages 4041200100077 are absent. 4041200100078 ENDBIB 76 0 4041200100079 NOCOMMON 0 0 4041200100080 ENDSUBENT 79 0 4041200199999 SUBENT 40412002 20140325 41634041200200001 BIB 3 25 4041200200002 REACTION (92-U-235(N,ABS),,ALF) ALF= Capture-to-fission CS 4041200200003 ratio for U-235 in the energy range from 10keV to 1MeV 4041200200004 ERR-ANALYS The uncertainties shown on the data are total error 4041200200005 which include standard deviation (ERR1) and systematic4041200200006 errors. Systematic errors due to the background sub- 4041200200007 traction (ERR2) ,to the measurement of the probability 4041200200008 that a fission event record as capture (ERR3),to the 4041200200009 measurement of the fission to capture efficiency ratio 4041200200010 (ERR4) and to the corrections (ERR5). These fractions 4041200200011 of total error are given in Table (in percent) 4041200200012 EN ERR1 ERR2 ERR3 ERR4 ERR5 ERR-T 4041200200013 KEV TOTAL 4041200200014 15. 8.0 18.0 2.6 7.0 2.0 21.2 4041200200015 25. 4.0 6.1 3.2 7.0 2.0 10.8 4041200200016 35. 3.5 3.5 3.0 7.0 2.0 9.3 4041200200017 45. 3.5 2.6 3.2 7.0 2.0 9.1 4041200200018 55. 2.5 2.4 3.4 7.0 2.0 8.8 4041200200019 65. 2.0 2.2 3.5 7.0 2.0 8.6 4041200200020 75. 2.0 2.1 3.6 7.0 2.0 8.6 4041200200021 185. 4.4 1.5 4.6 7.0 2.0 9.8 4041200200022 300. 6.1 1.0 5.4 7.0 2.0 11.0 4041200200023 500. 4.0 1.0 6.2 7.0 2.0 10.4 4041200200024 900. 10.0 2.0 9.0 7.0 2.0 15.4 4041200200025 STATUS Data for superseded Subentry 40073.002. 4041200200026 (TABLE) Revised by author data of Table II of R,FEI-2744041200200027 ENDBIB 25 0 4041200200028 NOCOMMON 0 0 4041200200029 DATA 4 47 4041200200030 EN EN-RSL DATA ERR-T 4041200200031 KEV KEV NO-DIM NO-DIM 4041200200032 1.2400E+01 7.0000E-01 5.8400E-01 1.3200E-01 4041200200033 1.3400E+01 8.0000E-01 5.0700E-01 1.2500E-01 4041200200034 1.4300E+01 8.0000E-01 4.8700E-01 1.1000E-01 4041200200035 1.5400E+01 9.0000E-01 5.6500E-01 1.1200E-01 4041200200036 1.5900E+01 1.0000E+00 4.8100E-01 9.8000E-02 4041200200037 1.6400E+01 1.0000E+00 4.5200E-01 9.3000E-02 4041200200038 1.6900E+01 1.1000E+00 3.8900E-01 8.2000E-02 4041200200039 1.7400E+01 1.1000E+00 3.7400E-01 7.6000E-02 4041200200040 1.7900E+01 1.2000E+00 4.2000E-01 8.1000E-02 4041200200041 1.8500E+01 1.2000E+00 4.5200E-01 8.0000E-02 4041200200042 1.9100E+01 1.3000E+00 3.9500E-01 6.8000E-02 4041200200043 1.9800E+01 1.4000E+00 3.6100E-01 6.7000E-02 4041200200044 2.0400E+01 1.4000E+00 3.3900E-01 5.2000E-02 4041200200045 2.1100E+01 1.5000E+00 3.2800E-01 4.3000E-02 4041200200046 2.1900E+01 1.6000E+00 3.6000E-01 5.3000E-02 4041200200047 2.2700E+01 1.7000E+00 3.6200E-01 4.4000E-02 4041200200048 2.3500E+01 1.8000E+00 3.6700E-01 4.4000E-02 4041200200049 2.4300E+01 1.9000E+00 3.5900E-01 4.1000E-02 4041200200050 2.5300E+01 2.0000E+00 3.0300E-01 3.6000E-02 4041200200051 2.6200E+01 2.0000E+00 2.8700E-01 3.6000E-02 4041200200052 2.7200E+01 2.2000E+00 3.1200E-01 3.4000E-02 4041200200053 2.8400E+01 2.4000E+00 3.3300E-01 3.6000E-02 4041200200054 2.9500E+01 2.5000E+00 3.5600E-01 3.7000E-02 4041200200055 3.0700E+01 2.7000E+00 3.6900E-01 3.9000E-02 4041200200056 3.2100E+01 2.8000E+00 3.7400E-01 3.9000E-02 4041200200057 3.3400E+01 3.0000E+00 3.6500E-01 3.7000E-02 4041200200058 3.4900E+01 3.2000E+00 3.7400E-01 3.7000E-02 4041200200059 3.6500E+01 3.4000E+00 3.6300E-01 3.8000E-02 4041200200060 3.8200E+01 3.7000E+00 3.6900E-01 3.7000E-02 4041200200061 4.0000E+01 3.9000E+00 3.5500E-01 3.6000E-02 4041200200062 4.2000E+01 4.2000E+00 3.5800E-01 3.6000E-02 4041200200063 4.4100E+01 4.6000E+00 3.2900E-01 3.0000E-02 4041200200064 4.6300E+01 4.9000E+00 3.2800E-01 3.2000E-02 4041200200065 4.8800E+01 5.3000E+00 3.2100E-01 3.3000E-02 4041200200066 5.1400E+01 5.7000E+00 3.0500E-01 3.1000E-02 4041200200067 5.4300E+01 6.2000E+00 3.0800E-01 3.2000E-02 4041200200068 5.7400E+01 6.8000E+00 2.9600E-01 3.0000E-02 4041200200069 6.5000E+01 5.0000E+00 2.9600E-01 2.5000E-02 4041200200070 7.5000E+01 5.0000E+00 2.8500E-01 2.5000E-02 4041200200071 1.3500E+02 2.5000E+01 2.6500E-01 2.8000E-02 4041200200072 1.8500E+02 1.5000E+01 2.3400E-01 2.3000E-02 4041200200073 3.0000E+02 1.0000E+01 1.9500E-01 2.1000E-02 4041200200074 4.0000E+02 1.0000E+01 1.9700E-01 2.1000E-02 4041200200075 5.0000E+02 1.0000E+01 1.6200E-01 1.7000E-02 4041200200076 7.5000E+02 3.0000E+01 1.3800E-01 1.9000E-02 4041200200077 9.0000E+02 3.0000E+01 1.1100E-01 1.7000E-02 4041200200078 1.1000E+03 3.0000E+01 8.5000E-02 1.5000E-02 4041200200079 ENDDATA 49 0 4041200200080 ENDSUBENT 79 0 4041200299999 SUBENT 40412003 20191209 41854041200300001 BIB 6 14 4041200300002 REACTION (92-U-235(N,F),,SIG,,AV) 4041200300003 MONITOR ((MONIT)92-U-235(N,F),,SIG,,AV) Average in energy range4041200300004 from EN-NRM-MIN to EN-NRM-MAX cross-section from 4041200300005 MONIT-REF, used for normalization. 4041200300006 MONIT-REF (,M.Sowerby+,R,AERE-R-7273,1973) 4041200300007 ERR-ANALYS (ERR-T) Total error 6.5% which includes 4041200300008 (ERR-S,,1.) Standard deviation (<1.0 percent), 4041200300009 (ERR-1) Uncertainty due to background subtraction 4041200300010 (ERR-2) Uncertainty in normalization 4041200300011 (ERR-3) Uncertainty in energy dependence of 4041200300012 10-B(n,alpha+gamma) cross-section 4041200300013 STATUS (TABLE) Table 1 of Reference rep.YK-15,p.12,1974 = 4041200300014 Table 1 of At.En.,v.38,is.2,p.82,1975 4041200300015 HISTORY (20191209A) Correction of ERR-ANALYS 4041200300016 ENDBIB 14 0 4041200300017 COMMON 6 3 4041200300018 ERR-1 ERR-2 ERR-3 EN-NRM-MIN EN-NRM-MAX MONIT 4041200300019 PER-CENT PER-CENT PER-CENT KEV KEV B 4041200300020 1.0 5.5 3. 30. 40. 2.011 4041200300021 ENDCOMMON 3 0 4041200300022 DATA 4 7 4041200300023 EN-MIN EN-MAX DATA ERR-T 4041200300024 KEV KEV B B 4041200300025 1.0000E+01 2.0000E+01 2.3570E+00 1.5300E-01 4041200300026 2.0000E+01 3.0000E+01 2.1790E+00 1.3900E-01 4041200300027 3.0000E+01 4.0000E+01 2.0110E+00 1.2900E-01 4041200300028 4.0000E+01 5.0000E+01 1.8890E+00 1.2100E-01 4041200300029 5.0000E+01 6.0000E+01 1.8520E+00 1.1900E-01 4041200300030 6.0000E+01 7.0000E+01 1.7680E+00 1.1300E-01 4041200300031 7.0000E+01 8.0000E+01 1.6680E+00 1.0700E-01 4041200300032 ENDDATA 9 0 4041200300033 ENDSUBENT 32 0 4041200399999 SUBENT 40412004 20191209 41854041200400001 BIB 4 11 4041200400002 REACTION (92-U-235(N,G)92-U-236,,SIG,,AV) 4041200400003 ANALYSIS Capture CS was determined from ALF and fission CS. 4041200400004 ERR-ANALYS (ERR-T) Errors shown on the data are total error 4041200400005 which includes error of alpha and fission cross-section4041200400006 data 4041200400007 (ERR-1) Uncertainty of fission C-S. 4041200400008 .See also uncertainties in Subents 002,003. 4041200400009 STATUS (TABLE) Revised by author data of Table 1 of 4041200400010 J.At.Energ.,v.38,is.2,p.82,1975 4041200400011 (DEP,40412002) ALFA 4041200400012 (DEP,40412003) Fission cross section 4041200400013 ENDBIB 11 0 4041200400014 COMMON 1 3 4041200400015 ERR-1 4041200400016 PER-CENT 4041200400017 6.5 4041200400018 ENDCOMMON 3 0 4041200400019 DATA 4 7 4041200400020 EN-MIN EN-MAX DATA ERR-T 4041200400021 KEV KEV B B 4041200400022 1.0000E+01 2.0000E+01 1.0470E+00 2.3200E-01 4041200400023 2.0000E+01 3.0000E+01 7.3900E-01 9.3000E-02 4041200400024 3.0000E+01 4.0000E+01 7.3600E-01 8.3000E-02 4041200400025 4.0000E+01 5.0000E+01 6.2700E-01 7.0000E-02 4041200400026 5.0000E+01 6.0000E+01 5.6900E-01 6.2000E-02 4041200400027 6.0000E+01 7.0000E+01 5.2300E-01 5.6000E-02 4041200400028 7.0000E+01 8.0000E+01 4.7500E-01 5.1000E-02 4041200400029 ENDDATA 9 0 4041200400030 ENDSUBENT 29 0 4041200499999 SUBENT 40412005 20140325 41634041200500001 BIB 3 25 4041200500002 REACTION (94-PU-239(N,ABS),,ALF) Capture/Fission cross section 4041200500003 ratio for Pu-239 in the energy range 4041200500004 ERR-ANALYS (ERR-T) errors shown on the data are total error 4041200500005 which includes standard deviation (ERR1) and systematic4041200500006 errors. Systematic errors due the background 4041200500007 subtraction (ERR2), the measurement of the probability44041200500008 that a fission event record as capture (ERR3), the 4041200500009 measurement of the fission to capture efficiency ratio 4041200500010 (ERR4) and to the corrections (ERR5). These fractions 4041200500011 of total error (in percent) are given in the Table 4041200500012 EN ERR1 ERR2 ERR3 ERR4 ERR5 ERR 4041200500013 KEV TOTAL 4041200500014 15. 6.0 19.0 3.7 7.0 2.0 21.5 4041200500015 25. 4.0 6.2 4.4 7.0 2.0 11.5 4041200500016 35. 3.0 4.2 5.1 7.0 2.0 10.3 4041200500017 45. 2.5 3.2 5.9 7.0 2.0 10.6 4041200500018 55. 2.0 3.0 7.2 7.0 2.0 10.9 4041200500019 65. 2.0 3.0 7.9 7.0 2.0 11.3 4041200500020 75. 2.0 3.0 8.4 7.0 2.0 11.7 4041200500021 185. 8.7 1.5 9.9 7.0 2.0 15.1 4041200500022 300. 11.7 2.0 10.9 7.0 2.0 17.6 4041200500023 500. 12.2 2.5 13.3 7.0 2.0 19.6 4041200500024 900. 18.8 3.0 30.0 7.0 2.0 36.3 4041200500025 STATUS Data for superseded Subentry 40073.003. 4041200500026 (TABLE)Revised by author data of Table III of R,FEI-2744041200500027 ENDBIB 25 0 4041200500028 NOCOMMON 0 0 4041200500029 DATA 4 52 4041200500030 EN EN-ERR DATA ERR-T 4041200500031 KEV KEV NO-DIM NO-DIM 4041200500032 9.4000E+00 5.0000E-01 5.6100E-01 1.6100E-01 4041200500033 1.0400E+01 5.0000E-01 5.6800E-01 1.4800E-01 4041200500034 1.1300E+01 6.0000E-01 6.3800E-01 1.4100E-01 4041200500035 1.2200E+01 7.0000E-01 5.7700E-01 1.4600E-01 4041200500036 1.3100E+01 7.0000E-01 6.0000E-01 1.4500E-01 4041200500037 1.4200E+01 8.0000E-01 5.3400E-01 1.1700E-01 4041200500038 1.5200E+01 9.0000E-01 4.6900E-01 1.1300E-01 4041200500039 1.5900E+01 1.0000E+00 4.1200E-01 9.2000E-02 4041200500040 1.6400E+01 1.0000E+00 3.8500E-01 9.0000E-02 4041200500041 1.6800E+01 1.1000E+00 3.7300E-01 8.1000E-02 4041200500042 1.7300E+01 1.1000E+00 3.6600E-01 7.8000E-02 4041200500043 1.7900E+01 1.2000E+00 3.7100E-01 7.6000E-02 4041200500044 1.8400E+01 1.2000E+00 3.5600E-01 7.0000E-02 4041200500045 1.9000E+01 1.3000E+00 3.7000E-01 7.2000E-02 4041200500046 1.9600E+01 1.4000E+00 3.8300E-01 6.9000E-02 4041200500047 2.0300E+01 1.4000E+00 3.9600E-01 6.3000E-02 4041200500048 2.0900E+01 1.5000E+00 3.8900E-01 5.1000E-02 4041200500049 2.1600E+01 1.6000E+00 3.8100E-01 4.6000E-02 4041200500050 2.2400E+01 1.7000E+00 3.5900E-01 4.3000E-02 4041200500051 2.3200E+01 1.7000E+00 3.5700E-01 4.5000E-02 4041200500052 2.4000E+01 1.8000E+00 3.3100E-01 4.0000E-02 4041200500053 2.4800E+01 1.9000E+00 3.2700E-01 3.9000E-02 4041200500054 2.5800E+01 2.0000E+00 3.4100E-01 4.2000E-02 4041200500055 2.6700E+01 2.2000E+00 3.1300E-01 3.7000E-02 4041200500056 2.7800E+01 2.3000E+00 3.0400E-01 3.6000E-02 4041200500057 2.8800E+01 2.4000E+00 2.9300E-01 3.7000E-02 4041200500058 3.0000E+01 2.6000E+00 2.5800E-01 3.0000E-02 4041200500059 3.1200E+01 2.7000E+00 2.6900E-01 3.0000E-02 4041200500060 3.2500E+01 2.9000E+00 2.8300E-01 3.1000E-02 4041200500061 3.3900E+01 3.1000E+00 2.9700E-01 3.3000E-02 4041200500062 3.5300E+01 3.3000E+00 2.7100E-01 3.1000E-02 4041200500063 3.6900E+01 3.5000E+00 2.7100E-01 2.8000E-02 4041200500064 3.8600E+01 3.4000E+00 2.5400E-01 2.8000E-02 4041200500065 4.0400E+01 4.0000E+00 2.5800E-01 2.9000E-02 4041200500066 4.2300E+01 4.3000E+00 2.5100E-01 2.7000E-02 4041200500067 4.4300E+01 4.6000E+00 2.3600E-01 2.5000E-02 4041200500068 4.6500E+01 4.9000E+00 2.2400E-01 2.4000E-02 4041200500069 4.8900E+01 5.3000E+00 2.1800E-01 2.4000E-02 4041200500070 5.1400E+01 5.7000E+00 2.0300E-01 2.3000E-02 4041200500071 5.4200E+01 6.2000E+00 1.8600E-01 2.2000E-02 4041200500072 5.7200E+01 6.7000E+00 1.8400E-01 2.2000E-02 4041200500073 6.5000E+01 5.0000E+00 1.6800E-01 1.9000E-02 4041200500074 7.5000E+01 5.0000E+00 1.4900E-01 1.7000E-02 4041200500075 1.1000E+02 2.0000E+01 1.5900E-01 1.9000E-02 4041200500076 1.5000E+02 2.0000E+01 1.2400E-01 1.9000E-02 4041200500077 1.8500E+02 1.5000E+01 9.9000E-02 1.7000E-02 4041200500078 3.0000E+02 1.0000E+01 1.1200E-01 2.0000E-02 4041200500079 4.0000E+02 1.0000E+01 8.4000E-02 1.7000E-02 4041200500080 5.0000E+02 1.0000E+01 9.1000E-02 1.8000E-02 4041200500081 7.5000E+02 3.0000E+01 8.0000E-02 1.7000E-02 4041200500082 9.0000E+02 3.0000E+01 4.1000E-02 1.5000E-02 4041200500083 1.0000E+03 3.0000E+01 1.7000E-02 3.1000E-02 4041200500084 ENDDATA 54 0 4041200500085 ENDSUBENT 84 0 4041200599999 SUBENT 40412006 20191209 41854041200600001 BIB 6 14 4041200600002 REACTION (94-PU-239(N,F),,SIG,,AV) 4041200600003 MONITOR ((MONIT)94-PU-239(N,F),,SIG,,AV) Average in energy 4041200600004 range from EN-NRM-MIN to EN-NRM-MAX cross-section from 4041200600005 MONIT-REF, used for normalization. 4041200600006 MONIT-REF (,M.Sowerby+,R,AERE-R-7273,1973) 4041200600007 ERR-ANALYS (ERR-T) Total error includes 4041200600008 (ERR-S,,1.) Standard deviation 4041200600009 (ERR-1) Uncertainty due to background subtraction 4041200600010 (ERR-2) Uncertainty in normalization 4041200600011 (ERR-3) Uncertainty in energy dependence of 4041200600012 10-B(n,alpha+gamma) cross-section 4041200600013 STATUS (TABLE) Table 2 of Reference rep.YK-15,p.12,1974 = 4041200600014 Table 2 of J.At.Energy,v.38,is.2,p.82,1975. 4041200600015 HISTORY (20191209A) Correction of ERR-ANALYS 4041200600016 ENDBIB 14 0 4041200600017 COMMON 6 3 4041200600018 ERR-1 ERR-2 ERR-3 EN-NRM-MIN EN-NRM-MAX MONIT 4041200600019 PER-CENT PER-CENT PER-CENT KEV KEV B 4041200600020 1.0 6.0 3.0 30. 40. 1.6 4041200600021 ENDCOMMON 3 0 4041200600022 DATA 4 7 4041200600023 EN-MIN EN-MAX DATA ERR-T 4041200600024 KEV KEV B B 4041200600025 1.0000E+01 2.0000E+01 1.6280E+00 1.1200E-01 4041200600026 2.0000E+01 3.0000E+01 1.6220E+00 1.1000E-01 4041200600027 3.0000E+01 4.0000E+01 1.6000E+00 1.0900E-01 4041200600028 4.0000E+01 5.0000E+01 1.5590E+00 1.0600E-01 4041200600029 5.0000E+01 6.0000E+01 1.5950E+00 1.0800E-01 4041200600030 6.0000E+01 7.0000E+01 1.5980E+00 1.0900E-01 4041200600031 7.0000E+01 8.0000E+01 1.5200E+00 1.0300E-01 4041200600032 ENDDATA 9 0 4041200600033 ENDSUBENT 32 0 4041200699999 SUBENT 40412007 20191209 41854041200700001 BIB 4 9 4041200700002 REACTION (94-PU-239(N,G)94-PU-240,,SIG,,AV) 4041200700003 ANALYSIS Capture CS was determined from ALF and fission CS. 4041200700004 ERR-ANALYS (DATA-ERR) Errors shown on the data are total error 4041200700005 which includes errors of alpha and fission cross- 4041200700006 section data . See also uncertainties in Subents 5,6. 4041200700007 STATUS (TABLE) Revised by author data of Table 2 of 4041200700008 J.At.Energy,v.38,is.2,p.82,1975. 4041200700009 (DEP,40412005) ALF 4041200700010 (DEP,40412006) Fission cross section 4041200700011 ENDBIB 9 0 4041200700012 NOCOMMON 0 0 4041200700013 DATA 4 7 4041200700014 EN-MIN EN-MAX DATA DATA-ERR 4041200700015 KEV KEV B B 4041200700016 1.0000E+01 2.0000E+01 7.0300E-01 1.5900E-01 4041200700017 2.0000E+01 3.0000E+01 5.3900E-01 7.1000E-02 4041200700018 3.0000E+01 4.0000E+01 4.3500E-01 5.4000E-02 4041200700019 4.0000E+01 5.0000E+01 3.6000E-01 4.5000E-02 4041200700020 5.0000E+01 6.0000E+01 3.0500E-01 3.9000E-02 4041200700021 6.0000E+01 7.0000E+01 2.6800E-01 3.5000E-02 4041200700022 7.0000E+01 8.0000E+01 2.2600E-01 3.1000E-02 4041200700023 ENDDATA 9 0 4041200700024 ENDSUBENT 23 0 4041200799999 SUBENT 40412008 20140325 41634041200800001 BIB 5 13 4041200800002 REACTION ((94-PU-239(N,F),,SIG,,AV)/(92-U-235(N,F),,SIG,,AV)) 4041200800003 Ratio of fission cross-sections of Pu-239 4041200800004 and U-235 in the energy range from 10 to 80 keV 4041200800005 MONITOR ((MONIT)(94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 4041200800006 Used for normalization. 4041200800007 MONIT-REF (,M.Sowerby+,R,AERE-R-7273,1973) 4041200800008 ERR-ANALYS (ERR-T) Total error - 3%. 4041200800009 (ERR-S) Statistical error 4041200800010 (ERR-2) Systematic error, mainly due to background 4041200800011 subtraction. 4041200800012 (ERR-1) Error of normalization. 4041200800013 STATUS (TABLE) Table 2 Reference YK-15,12,1974 = Table 2 of 4041200800014 Reference AE,38,(2),82,1975. 4041200800015 ENDBIB 13 0 4041200800016 COMMON 7 6 4041200800017 ERR-S ERR-2 ERR-1 EN-NRM-MIN EN-NRM-MAX MONIT 4041200800018 MONIT-ERR 4041200800019 PER-CENT PER-CENT PER-CENT KEV KEV NO-DIM 4041200800020 NO-DIM 4041200800021 1.0 1.5 2.5 30. 40. 0.796 4041200800022 0.020 4041200800023 ENDCOMMON 6 0 4041200800024 DATA 4 7 4041200800025 EN-MIN EN-MAX DATA ERR-T 4041200800026 KEV KEV NO-DIM NO-DIM 4041200800027 1.0000E+01 2.0000E+01 6.9100E-01 2.1000E-02 4041200800028 2.0000E+01 3.0000E+01 7.5500E-01 2.3000E-02 4041200800029 3.0000E+01 4.0000E+01 7.9600E-01 2.4000E-02 4041200800030 4.0000E+01 5.0000E+01 8.2500E-01 2.5000E-02 4041200800031 5.0000E+01 6.0000E+01 8.6100E-01 2.6000E-02 4041200800032 6.0000E+01 7.0000E+01 9.0400E-01 2.7000E-02 4041200800033 7.0000E+01 8.0000E+01 9.1100E-01 2.7000E-02 4041200800034 ENDDATA 9 0 4041200800035 ENDSUBENT 34 0 4041200899999 ENDENTRY 8 0 4041299999999