ENTRY 40861 20130822 41614086100000001 SUBENT 40861001 20130822 41614086100100001 BIB 11 35 4086100100002 INSTITUTE (4RUSFEI) 4086100100003 REFERENCE (J,AE,58,(2),137,198502) Data table is given 4086100100004 (J,SJA,58,163,1985)Eng.trans.of J,AE,58,137,1985 4086100100005 #doi:10.1007/BF01122211 4086100100006 AUTHOR (A.A.Goverdovskii, A.K.Gordyushin, B.D.Kuz'minow, 4086100100007 V.F.Mitrofanov, A.I.Sergachev, S.M.Solov'ev, 4086100100008 G.M.Stepchenkova) 4086100100009 TITLE Measurement of the ratio of the cross sections for 4086100100010 fissioning of Np-237 and U-235 by neutrons with 4086100100011 energies in range 4 - 11 MeV. 4086100100012 FACILITY (VDG,4RUSFEI)Charge exchange electrostatic accelerator 4086100100013 INC-SOURCE (D-D) Gas target at pressure 1.2E+5 Pa.Average deuteron4086100100014 current 1.5 microA. 4086100100015 INC-SPECT Mono-energy neutrons. For En > 5 MeV - there is a 4086100100016 background due to d(d,np)d reaction of continuous 4086100100017 spectrum with average energy about 3 MeV and intensity 4086100100018 comparative with one of mono-line in energy range 4086100100019 En > 8.5 MeV. 4086100100020 DETECTOR (IOCH) Double ionization chamber for fission fragments.4086100100021 Filled with methane at 1.8E+5 Pa pressure. 4086100100022 (SCIN) For neutron flux monitoring 4086100100023 Cf-252 source was used in gamma-fission fragment 4086100100024 coincidence technique. 4086100100025 STATUS (APRVD) Under question 4086100100026 CORRECTION On neutron background calculated by Monte-Carlo method4086100100027 On fission of the admixture nuclides - 0.11 to 0.3 %. 4086100100028 On fission fragments deceleration - up to 0.12 %. 4086100100029 On homogeneity violation - up to 0.4 % . 4086100100030 HISTORY (19850517C) 4086100100031 (20130822A) M.M. Upper -> lower case correction. 4086100100032 Dates were corrected for 4-digits year. 4086100100033 Reference of Engl.translation was added. 4086100100034 BIB information was updated. 4086100100035 ERR-ANALYS in Subent 004 was corrected according to 4086100100036 now-days rules. 4086100100037 ENDBIB 35 0 4086100100038 NOCOMMON 0 0 4086100100039 ENDSUBENT 38 0 4086100199999 SUBENT 40861002 20130822 41614086100200001 BIB 5 18 4086100200002 REACTION ((93-NP-237(N,F),,SIG)/(92-U-235(N,F),,SIG)) 4086100200003 SAMPLE Seven samples were used for normalization cross-section4086100200004 measurements. Table which follows gives samples 4086100200005 properties. 4086100200006 Sample number/U-235 content/NP-237 content/Thickness 4086100200007 3. 3.46 % 96.54 % 300 microg/cm2 4086100200008 4. 4.40 % 95.60 % 300 microg/cm2 4086100200009 5. 6.50 % 93.50 % 300 microg/cm2 4086100200010 6. 18.26 % 81.74 % 300 microg/cm2 4086100200011 7. 24.65 % 75.35 % 100 microg/cm2 4086100200012 8. 34.75 % 65.25 % 98 microg/cm2 4086100200013 9. 5.19 % 94.81 % 204 microg/cm2 4086100200014 Samples 3-8 were of 99.9% purity. 4086100200015 Sample 9 was mixture of U-238 and U-235 4086100200016 MISC-COL (MISC) Thickness of sample. 4086100200017 STATUS (TABLE) Table 1 of J,AE,58,(2),137,19850 4086100200018 HISTORY (20130822A) M.M. THICKNESS -> MISC was corrected 4086100200019 according to opinion of N.Otsuka (NDS,IAEA) . 4086100200020 ENDBIB 18 0 4086100200021 NOCOMMON 0 0 4086100200022 DATA 3 28 4086100200023 EN DATA MISC 4086100200024 MEV NO-DIM G/CM-SQ 4086100200025 6.5500E+00 1.3350E+00 9.8000E-05 4086100200026 6.5500E+00 1.3000E+00 1.0000E-04 4086100200027 6.5500E+00 1.3300E+00 2.0400E-04 4086100200028 6.5500E+00 1.3200E+00 3.0000E-04 4086100200029 6.5500E+00 1.3280E+00 3.0000E-04 4086100200030 6.5500E+00 1.3120E+00 3.0000E-04 4086100200031 6.5500E+00 1.3100E+00 3.0600E-04 4086100200032 6.9500E+00 1.2700E+00 9.8000E-05 4086100200033 6.9500E+00 1.2620E+00 1.0000E-04 4086100200034 6.9500E+00 1.2860E+00 2.0400E-04 4086100200035 6.9500E+00 1.2600E+00 3.0000E-04 4086100200036 6.9500E+00 1.2420E+00 3.0000E-04 4086100200037 6.9500E+00 1.2720E+00 3.0000E-04 4086100200038 6.9500E+00 1.2500E+00 3.0600E-04 4086100200039 7.3400E+00 1.1740E+00 9.8000E-05 4086100200040 7.3400E+00 1.1800E+00 1.0000E-04 4086100200041 7.3400E+00 1.2090E+00 2.0400E-04 4086100200042 7.3400E+00 1.1900E+00 3.0000E-04 4086100200043 7.3400E+00 1.2300E+00 3.0000E-04 4086100200044 7.3400E+00 1.2260E+00 3.0000E-04 4086100200045 7.3400E+00 1.2320E+00 3.0600E-04 4086100200046 7.7500E+00 1.1760E+00 9.8000E-05 4086100200047 7.7500E+00 1.2210E+00 1.0000E-04 4086100200048 7.7500E+00 1.1950E+00 2.0400E-04 4086100200049 7.7500E+00 1.1750E+00 3.0000E-04 4086100200050 7.7500E+00 1.2000E+00 3.0000E-04 4086100200051 7.7500E+00 1.1890E+00 3.0000E-04 4086100200052 7.7500E+00 1.2090E+00 3.0600E-04 4086100200053 ENDDATA 30 0 4086100200054 ENDSUBENT 53 0 4086100299999 SUBENT 40861003 20130822 41614086100300001 BIB 4 7 4086100300002 REACTION ((93-NP-237(N,F),,SIG)/(92-U-235(N,F),,SIG)) 4086100300003 ANALYSIS Averaged values of several samples. 4086100300004 ERR-ANALYS (ERR-1) Isotopic content error 4086100300005 (ERR-2) Uncertainty of ratio of detectors efficiencies 4086100300006 for Np-237 fission to U-235 one. 4086100300007 STATUS (TABLE) Table 1 of J,AE,58,(2),137,19850 4086100300008 (DEP,40861002) See ANALYSIS 4086100300009 ENDBIB 7 0 4086100300010 COMMON 2 3 4086100300011 ERR-1 ERR-2 4086100300012 PER-CENT PER-CENT 4086100300013 1.0000E+00 4.0000E-01 4086100300014 ENDCOMMON 3 0 4086100300015 DATA 3 4 4086100300016 EN DATA ERR-T 4086100300017 MEV NO-DIM NO-DIM 4086100300018 6.5500E+00 1.3190E+00 1.6000E-02 4086100300019 6.9500E+00 1.2630E+00 1.5000E-02 4086100300020 7.3400E+00 1.2060E+00 1.5000E-02 4086100300021 7.7500E+00 1.1950E+00 1.4000E-02 4086100300022 ENDDATA 6 0 4086100300023 ENDSUBENT 22 0 4086100399999 SUBENT 40861004 20130822 41614086100400001 BIB 6 18 4086100400002 REACTION ((93-NP-237(N,F),,SIG)/(92-U-235(N,F),,SIG)) 4086100400003 SAMPLE Two high-purity samples of neptunium and uranium 4086100400004 oxides were used.1-st sample contains 99.992 % 4086100400005 of U-235, thickness 410 and 256 microgram/cm2, 4086100400006 2nd sample contains 99.05% of Np-237, 0.52% of Am-241 4086100400007 and 0.43 % of Pu-239, thickness 460 microgram/cm2 4086100400008 FLAG (1.) Normalization values (four points) 4086100400009 ANALYSIS Energy dependence of c-s ratio was measured by two 4086100400010 isotopically pure samples. Then this dependence was 4086100400011 normalized by values obtained by samples 3-9. 4086100400012 ERR-ANALYS (ERR-1,0.3,0.6) Detection efficiency ratio error 4086100400013 (ERR-2) Normalization error 4086100400014 (ERR-3,,0.1) Error arising due to the corrections 4086100400015 (ERR-4,0.10,0.45) Uncertainty due to background 4086100400016 subtraction for neutron energies > 8 MeV. 4086100400017 (ERR-S) Statistical uncertainty 0.8 - 1.1 %. 4086100400018 STATUS (TABLE) Table 2 of J,AE,58,(2),137,19850 4086100400019 (DEP,40861003) See ANALYSIS. 4086100400020 ENDBIB 18 0 4086100400021 COMMON 1 3 4086100400022 ERR-2 4086100400023 PER-CENT 4086100400024 0.85 4086100400025 ENDCOMMON 3 0 4086100400026 DATA 6 35 4086100400027 EN EN-RSL-FW DATA ERR-S ERR-T FLAG 4086100400028 MEV KEV NO-DIM PER-CENT PER-CENT NO-DIM 4086100400029 4.4400E+00 1.5000E+02 1.3630E+00 1.0000E+00 1.3700E+00 4086100400030 4.9700E+00 1.3000E+02 1.4200E+00 9.2000E-01 1.3200E+00 4086100400031 5.2100E+00 1.2300E+02 1.4160E+00 9.4000E-01 1.3300E+00 4086100400032 5.4400E+00 1.2000E+02 1.4490E+00 1.0500E+00 1.4100E+00 4086100400033 5.6600E+00 1.1600E+02 1.4580E+00 1.0700E+00 1.4300E+00 4086100400034 5.8800E+00 1.0900E+02 1.4810E+00 9.3000E-01 1.3200E+00 4086100400035 6.1100E+00 1.0200E+02 1.4340E+00 8.9000E-01 1.3000E+00 4086100400036 6.1400E+00 1.0200E+02 1.4090E+00 1.1100E+00 1.4600E+00 4086100400037 6.3500E+00 9.8000E+01 1.3610E+00 1.0700E+00 1.4300E+00 4086100400038 6.3800E+00 9.6000E+01 1.3650E+00 9.5000E-01 1.3400E+00 4086100400039 6.5500E+00 9.2000E+01 1.3190E+00 4.5000E-01 1.2100E+00 1.0000E+004086100400040 6.7500E+00 8.8000E+01 1.2620E+00 1.1600E+00 1.5000E+00 4086100400041 6.9500E+00 8.4000E+01 1.2630E+00 4.8000E-01 1.1900E+00 1.0000E+004086100400042 7.1500E+00 8.1000E+01 1.2130E+00 1.1000E+00 1.4500E+00 4086100400043 7.3400E+00 8.1000E+01 1.2130E+00 1.1000E+00 1.4500E+00 1.0000E+004086100400044 7.5300E+00 7.5000E+01 1.1980E+00 1.2100E+00 1.5300E+00 4086100400045 7.7500E+00 7.3000E+01 1.1950E+00 5.4000E-01 1.1700E+00 1.0000E+004086100400046 7.9400E+00 7.0000E+01 1.1720E+00 1.0800E+00 1.4300E+00 4086100400047 8.1200E+00 6.8000E+01 1.1690E+00 1.0000E+00 1.3700E+00 4086100400048 8.3100E+00 6.6000E+01 1.1720E+00 1.1200E+00 1.4800E+00 4086100400049 8.5000E+00 6.4000E+01 1.1590E+00 8.9000E-01 1.3000E+00 4086100400050 8.6600E+00 6.3000E+01 1.1540E+00 9.0000E-01 1.3300E+00 4086100400051 8.8200E+00 6.2000E+01 1.1630E+00 7.8000E-01 1.2500E+00 4086100400052 9.0100E+00 6.0000E+01 1.1450E+00 8.6000E-01 1.3400E+00 4086100400053 9.1800E+00 5.9000E+01 1.1420E+00 9.9000E-01 1.4200E+00 4086100400054 9.3500E+00 5.8000E+01 1.1260E+00 9.0000E-01 1.3400E+00 4086100400055 9.5100E+00 5.6000E+01 1.1270E+00 1.0800E+00 1.4900E+00 4086100400056 9.6500E+00 5.5000E+01 1.1230E+00 1.0000E+00 1.4200E+00 4086100400057 9.8200E+00 5.4000E+01 1.1290E+00 1.1000E+00 1.5000E+00 4086100400058 9.9600E+00 5.3000E+01 1.1200E+00 1.1200E+00 1.5500E+00 4086100400059 1.0110E+01 5.3000E+01 1.1150E+00 1.0000E+00 1.4700E+00 4086100400060 1.0220E+01 5.2000E+01 1.1250E+00 9.0000E-01 1.4000E+00 4086100400061 1.0360E+01 5.2000E+01 1.1320E+00 1.0500E+00 1.5000E+00 4086100400062 1.0490E+01 5.0000E+01 1.1200E+00 1.1500E+00 1.5700E+00 4086100400063 1.0690E+01 5.0000E+01 1.1270E+00 1.2000E+00 1.6100E+00 4086100400064 ENDDATA 37 0 4086100400065 ENDSUBENT 64 0 4086100499999 ENDENTRY 4 0 4086199999999