ENTRY 32625 20181226 31873262500000001 SUBENT 32625001 20181226 31873262500100001 BIB 9 44 3262500100002 TITLE Measurement of U-233 fission cross section in fast 3262500100003 neutron energy region 3262500100004 AUTHOR (Yan Wuguang, Ye Zongyuan, Yuan Hanrong, Jia Wenhai, 3262500100005 Liu Bingguang, Zhou Xianjian, Ye Chuntang) 3262500100006 INSTITUTE (3CPRAEP) 3262500100007 REFERENCE (J,CST,9,133,1975) in Chinese 3262500100008 (S,IAEA-TECDOC-336,335,1985) Abstract in English, NDG. 3262500100009 FACILITY (CCW,3CPRAEP) 200 kV Cockcroft Walton accelerator 3262500100010 (VDG,3CPRAEP) 2.5 MV Van De Graaff 3262500100011 (VDG,3CPRFUD) 3.0 MV Van De Graaff 3262500100012 INC-SOURCE (P-LI7,P-T,D-D,D-T) 3262500100013 ------------------------------------------------------ 3262500100014 En (MeV) Neutron source 3262500100015 ------------------------------------------------------ 3262500100016 0.030 7Li(p,n) VdG (2.5 MV) Ep=1.883 MeV 3262500100017 0.12 to 0.50 7Li(p,n) VdG (2.5 MV) Ep=1.9 to 2.3 MeV 3262500100018 0.50 to 1.65 T(p,n) VdG (2.5 MV) Ep=1.2 to 2.5 MeV 3262500100019 1.60 to 2.20 T(p,n) VdG (3.0 MV) Ep=2.3 to 2.8 MeV 3262500100020 2.5 to 3.0 D(d,n) CcW Ed=0.2 MeV 3262500100021 3.0 to 5.6 D(d,n) VdG (2.5 MV) Ed=0.5 to 2.5 MeV 3262500100022 14 to 15 T(d,n) CcW Ed=0.2 MeV 3262500100023 15 to 18 T(d,n) VdG (2.5 MV) Ed=0.5 to 2.5 MeV 3262500100024 ------------------------------------------------------ 3262500100025 SAMPLE Uranium (26 mm in diameter, 200 ug/cm2 thick) was 3262500100026 electroplated on a Pt foil. 3262500100027 The total weight was 1.103+/-0.012 mg for U-233 sample 3262500100028 and 1.182+/-0.018 mg for U-235 sample. 3262500100029 ------------------------------------------------------ 3262500100030 Isotope U-233 sample U-235 sample 3262500100031 ------------------------------------------------------ 3262500100032 92-U-233 ENR=0.990+/-0.005 3262500100033 92-U-234 ENR=0.004+/-0.001 ENR=0.010+/-0.001 3262500100034 92-U-235 ENR=0.004+/-0.001 ENR=0.905+/-0.009 3262500100035 92-U-238 ENR=0.002+/-0.001 ENR=0.085+/-0.008 3262500100036 ------------------------------------------------------ 3262500100037 DETECTOR (LONGC) To monitor neutron flux at 60 deg 3262500100038 (FISCH) A back-to-back ionization chamber filled with 3262500100039 1 atoms Ar and methane (5-10%) 3262500100040 HISTORY (19950310C) Compiled by Liang Qichang (CNDC) 3262500100041 (20070820A) SD. BIB section was updated. Data 3262500100042 headings for uncertainties were changed. 3262500100043 (20180724A) On. Major revisions in 002 and 003 3262500100044 (20181226A) Wang Jimin (CNDC). 002 and 003 were 3262500100045 revised, 004 was added 3262500100046 ENDBIB 44 0 3262500100047 NOCOMMON 0 0 3262500100048 ENDSUBENT 47 0 3262500199999 SUBENT 32625002 20181226 31873262500200001 BIB 6 34 3262500200002 REACTION (92-U-233(N,F),,SIG) 3262500200003 DETECTOR (PROPC) Hydrogeneous proportional counter for flux 3262500200004 determination 3262500200005 CORRECTION Corrected for 3262500200006 . background 3262500200007 . fission detection efficiency 3262500200008 . fission counts due to other fission isotopes in the 3262500200009 U-233 sample 3262500200010 . fission fragments self-absorption in sample and 3262500200011 momentum effect resulting from the nuclear recoil 3262500200012 generated by neutron induced fission 3262500200013 . neutrons back-scatter by the platinum backing of 3262500200014 fission sample, and neutron absorption in the wall 3262500200015 and Cd cover of ionization chamber 3262500200016 . scattering neutrons from target tube, target cooling 3262500200017 water, and target backing 3262500200018 . solid angle and neutron beam angular distribution 3262500200019 ERR-ANALYS (ERR-T) Total errors which main sources are 3262500200020 (ERR-1) Sample weight (1.1%)3262500200021 (ERR-2) Fission detection efficiency (0.6%)3262500200022 (ERR-3,,0.04) Fission of other isotopes (<0.04%)3262500200023 (ERR-S) Fission and neutron counting statistics (1%)3262500200024 (ERR-4) Distance between sample and neutron source (2%)3262500200025 (ERR-5) Neutron detection efficiency (3%)3262500200026 (ERR-6) Fission fragments self-absorption (2%)3262500200027 (ERR-7) Neutron scattered by Pt backing and absorption 3262500200028 in wall and Cd cover of ionization chamber (3%)3262500200029 (ERR-8) Neutrons scattered by target tube, target 3262500200030 cooling water and target backing (0.4%)3262500200031 (ERR-9) Solid angle & beam angular distribution (0.6%)3262500200032 STATUS (TABLE) Table 6 of At.Energ.Sci.Technol.9(1975)133 3262500200033 HISTORY (20180724A) On. ERR-ANALYS moved from 001 and revised. 3262500200034 (20181226A) Wang Jimin (CNDC), CORRECTION moved from 3262500200035 001 and revised. 3262500200036 ENDBIB 34 0 3262500200037 COMMON 9 6 3262500200038 ERR-1 ERR-2 ERR-S ERR-4 ERR-5 ERR-6 3262500200039 ERR-7 ERR-8 ERR-9 3262500200040 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3262500200041 PER-CENT PER-CENT PER-CENT 3262500200042 1.1 0.6 1. 2. 3. 2.3262500200043 3. 0.4 0.6 3262500200044 ENDCOMMON 6 0 3262500200045 DATA 3 2 3262500200046 EN DATA ERR-T 3262500200047 MEV B B 3262500200048 0.5 1.962 0.098 3262500200049 1.0 1.964 0.098 3262500200050 ENDDATA 4 0 3262500200051 ENDSUBENT 50 0 3262500299999 SUBENT 32625003 20181226 31873262500300001 BIB 6 34 3262500300002 REACTION (92-U-235(N,F),,SIG) 3262500300003 DETECTOR (PROPC) Hydrogeneous proportional counter for flux 3262500300004 determination 3262500300005 CORRECTION Corrected for 3262500300006 . background 3262500300007 . fission detection efficiency 3262500300008 . fission counts due to other fission isotopes in the 3262500300009 U-235 sample 3262500300010 . fission fragments self-absorption in sample and 3262500300011 momentum effect resulting from the nuclear recoil 3262500300012 generated by neutron induced fission 3262500300013 . neutrons back-scatter by the platinum backing of 3262500300014 fission sample, and neutron absorption in the wall 3262500300015 and Cd cover of ionization chamber 3262500300016 . scattering neutrons from target tube, target cooling 3262500300017 water, and target backing 3262500300018 . solid angle and neutron beam angular distribution 3262500300019 ERR-ANALYS (ERR-T) Total errors which main sources are 3262500300020 (ERR-1) Sample weight (1.5%)3262500300021 (ERR-2) Fission detection efficiency (0.4%)3262500300022 (ERR-3) Fission of other isotopes (0.1%)3262500300023 (ERR-S) Fission and neutron counting statistics (1%)3262500300024 (ERR-4) Distance between sample and neutron source (2%)3262500300025 (ERR-5) Neutron detection efficiency (3%)3262500300026 (ERR-6) Fission fragments self-absorption (2%)3262500300027 (ERR-7) Neutron scattered by Pt backing and absorption 3262500300028 in wall and Cd cover of ionization chamber (3%)3262500300029 (ERR-8) Neutrons scattered by target tube, target 3262500300030 cooling water and target backing (0.4%)3262500300031 (ERR-9) Solid angle & beam angular distribution (0.6%)3262500300032 STATUS (TABLE) Table 6 of At.Energ.Sci.Technol.9(1975)133 3262500300033 HISTORY (20180724A) On. ERR-ANALYS moved from 001 and revised. 3262500300034 (20181226A) Wang Jimin (CNDC), CORRECTION moved from 3262500300035 001 and revised. 3262500300036 ENDBIB 34 0 3262500300037 COMMON 10 6 3262500300038 ERR-1 ERR-2 ERR-3 ERR-S ERR-4 ERR-5 3262500300039 ERR-6 ERR-7 ERR-8 ERR-9 3262500300040 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3262500300041 PER-CENT PER-CENT PER-CENT PER-CENT 3262500300042 1.5 0.4 0.1 1. 2. 3.3262500300043 2. 3. 0.4 0.6 3262500300044 ENDCOMMON 6 0 3262500300045 DATA 3 2 3262500300046 EN DATA ERR-T 3262500300047 MEV B B 3262500300048 0.5 1.148 0.058 3262500300049 1.0 1.243 0.063 3262500300050 ENDDATA 4 0 3262500300051 ENDSUBENT 50 0 3262500399999 SUBENT 32625004 20181226 31873262500400001 BIB 5 23 3262500400002 REACTION ((92-U-233(N,F),,SIG)/(92-U-235(N,F),,SIG)) 3262500400003 CORRECTION Corrected for 3262500400004 . fission counts due to other fission isotopes in the 3262500400005 U-233 and U-235 samples 3262500400006 . fission fragments self-absorption in sample and 3262500400007 momentum effect resulting from the nuclear recoil 3262500400008 generated by neutron induced fission 3262500400009 . interference neutrons from D(d,n) reaction in the 3262500400010 T(d,n) neutron source 3262500400011 . fission detection efficiency for U-233 and U-235 3262500400012 ERR-ANALYS (ERR-T) Total errors which main sources are 3262500400013 (ERR-1,1.,2.) Ratio calculation (1%-2%)3262500400014 (ERR-2) U-235 sample weight (1.5%)3262500400015 (ERR-3) U-233 sample weight (1.1%)3262500400016 (ERR-4) U-235 fission detection efficiency (0.2%)3262500400017 (ERR-5) U-233 fission detection efficiency (0.3%)3262500400018 (ERR-6) Fission fragments self-absorption (0.15%)3262500400019 (ERR-7,,0.1) Fission counts due to other isotopes 3262500400020 in U-235 sample (<0.1%)3262500400021 (ERR-8,,0.6) Fission counts due to other isotopes 3262500400022 in U-233 sample (<0.6%)3262500400023 STATUS (CURVE) Fig 3 and 4 of At.Energ.Sci.Technol.9(1975)133 3262500400024 HISTORY (20181226C) Wang Jimin (CNDC), 004 was added. 3262500400025 ENDBIB 23 0 3262500400026 COMMON 5 3 3262500400027 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 3262500400028 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3262500400029 1.5 1.1 0.2 0.3 0.15 3262500400030 ENDCOMMON 3 0 3262500400031 DATA 3 61 3262500400032 EN DATA ERR-T 3262500400033 MEV NO-DIM NO-DIM 3262500400034 0.030 1.38545 0.02651 3262500400035 0.115 1.51316 0.02861 3262500400036 0.140 1.58985 0.02791 3262500400037 0.185 1.63002 0.02861 3262500400038 0.235 1.64511 0.02721 3262500400039 0.285 1.65371 0.03419 3262500400040 0.315 1.65344 0.02721 3262500400041 0.330 1.63749 0.00000 3262500400042 0.380 1.64807 0.00000 3262500400043 0.405 1.65258 0.03628 3262500400044 0.435 1.64919 0.00000 3262500400045 0.480 1.69855 0.02791 3262500400046 0.520 1.69404 0.00000 3262500400047 0.540 1.71278 0.00000 3262500400048 0.575 1.71815 0.03070 3262500400049 0.620 1.71928 0.00000 3262500400050 0.660 1.67782 0.02582 3262500400051 0.720 1.67626 0.00000 3262500400052 0.730 1.68797 0.00000 3262500400053 0.760 1.68008 0.02930 3262500400054 0.805 1.67331 0.00000 3262500400055 0.840 1.64259 0.00000 3262500400056 0.870 1.65977 0.02512 3262500400057 0.950 1.58083 0.00000 3262500400058 0.951 1.59930 0.00000 3262500400059 0.970 1.57336 0.00000 3262500400060 0.975 1.58802 0.00000 3262500400061 0.980 1.53684 0.00000 3262500400062 1.010 1.53788 0.00000 3262500400063 1.075 1.51717 0.02442 3262500400064 1.120 1.52222 0.00000 3262500400065 1.185 1.50758 0.00000 3262500400066 1.230 1.52323 0.02930 3262500400067 1.325 1.52323 0.02861 3262500400068 1.445 1.55556 0.00000 3262500400069 1.545 1.52071 0.02930 3262500400070 1.635 1.52222 0.00000 3262500400071 1.665 1.50455 0.00000 3262500400072 1.745 1.53182 0.00000 3262500400073 1.805 1.49242 0.00000 3262500400074 1.925 1.53182 0.00000 3262500400075 2.015 1.51667 0.02442 3262500400076 2.480 1.55606 0.02512 3262500400077 2.860 1.56717 0.02651 3262500400078 3.045 1.52727 0.02791 3262500400079 3.290 1.51212 0.00000 3262500400080 3.630 1.56010 0.02791 3262500400081 3.930 1.54141 0.02861 3262500400082 4.205 1.51212 0.02721 3262500400083 4.295 1.50404 0.00000 3262500400084 4.595 1.47020 0.02930 3262500400085 5.010 1.47424 0.02930 3262500400086 5.345 1.49192 0.00000 3262500400087 5.525 1.48232 0.00000 3262500400088 5.640 1.47323 0.02651 3262500400089 13.745 1.13214 0.03070 3262500400090 14.785 1.14888 0.02651 3262500400091 15.255 1.10562 0.02861 3262500400092 16.325 1.09934 0.02442 3262500400093 17.200 1.15446 0.02721 3262500400094 18.400 1.15097 0.02791 3262500400095 ENDDATA 63 0 3262500400096 ENDSUBENT 95 0 3262500499999 ENDENTRY 4 0 3262599999999