ENTRY 32724 20181121 31873272400000001 SUBENT 32724001 20181121 31873272400100001 BIB 10 44 3272400100002 TITLE Measurement of 239Pu(n,f)/235U(n,f) cross section 3272400100003 ratio at the fast neutron energy region 3272400100004 AUTHOR (Deng Xinlu, Yan Wuguang, Zhou Xianjian, Ye Zongyuan, 3272400100005 Wu Jingxia, Rong Chaofan, Yuan Hanrong, Ye Chuntang, 3272400100006 Zhou Huiming) 3272400100007 INSTITUTE (3CPRAEP) 3272400100008 REFERENCE (J,CST,15,12,1981) 3272400100009 FACILITY (VDG,3CPRAEP) 2.5 MV Van de Graaff 3272400100010 (CCW,3CPRAEP) 600 kV Cockcroft-Walton accelerator 3272400100011 INC-SOURCE (P-LI7,P-T,D-D,D-T) 3272400100012 --------------------------------------------------- 3272400100013 En (MeV) Neutron source 3272400100014 --------------------------------------------------- 3272400100015 0.030 7Li(p,n) VdG Ep=1.883 MeV 3272400100016 0.12 to 0.50 7Li(p,n) VdG Ep=1.9 to 2.3 MeV 3272400100017 0.50 to 1.65 T(p,n) VdG Ep=1.2 to 2.5 MeV 3272400100018 2.5 to 3.0 D(d,n) CcW Ed=0.2 MeV 3272400100019 3.0 to 5.6 D(d,n) VdG Ed=0.5 to 2.5 MeV 3272400100020 14 to 15 T(d,n) CcW Ed=0.2 MeV 3272400100021 15 to 18 T(d,n) VdG Ed=0.5 to 2.5 MeV 3272400100022 --------------------------------------------------- 3272400100023 SAMPLE Pu and U (26 mm diam., ~200 ug/cm2 thick) 3272400100024 electrodeposited on Pt foil (20 um thick, 40 mm diam.) 3272400100025 (94-PU-239,ENR=0.969) 3272400100026 239Pu (96.9+/-0.8%) 3272400100027 240Pu (3.0+/-0.5%) 3272400100028 241Pu (0.1+/-0.1%) 3272400100029 1.020+/-0.010 mg. (2.490+/-0.026)E+18 239Pu atoms. 3272400100030 (92-U-235,ENR=0.905) 3272400100031 235U (90.5+/-0.9%) 3272400100032 234U (1.0+/-0.1%) 3272400100033 238U (8.5+/-0.8%) 3272400100034 1.173+/-0.017 mg. (2.739+/-0.041) E+18 235U atoms. 3272400100035 DETECTOR (FISCH) Cylindrical fission ionization chamber (100 3272400100036 mm in diam.) filled with methan (1 atm) at 0 deg. 3272400100037 (LONGC) To monitor neutron flux at 0 and 30 deg. 3272400100038 CORRECTION Corrected for 3272400100039 - Fission induced by other Pu and U isotopes 3272400100040 - Self-absorption of fission fragments 3272400100041 - The momentum effects of fission nucleus recoil 3272400100042 induced by incident neutrons, about +/-1.3% for 3272400100043 above 13.3 MeV and about +/- 1% for below 5.7 MeV 3272400100044 - D(d,n) neutrons (~2%) 3272400100045 HISTORY (20181121C) Wang Jimin (CNDC) + Otuka Naohiko (NDS) 3272400100046 ENDBIB 44 0 3272400100047 NOCOMMON 0 0 3272400100048 ENDSUBENT 47 0 3272400199999 SUBENT 32724002 20181121 31873272400200001 BIB 3 14 3272400200002 REACTION ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 3272400200003 ERR-ANALYS (ERR-T,2.0,2.6) Total uncertainty (2.0-2.6%) 3272400200004 (ERR-S,1.,2.) Counting statistics (1-2%) 3272400200005 (ERR-1) 235U sample mass (1.5%) 3272400200006 (ERR-2) 239Pu sample mass (1.0%) 3272400200007 (ERR-3) Reproducibility (0.9%) 3272400200008 (ERR-4) 235U(n,f) detection efficiency (0.2%) 3272400200009 (ERR-5) 239Pu(n,f) detection efficiency (1.4%) 3272400200010 (ERR-6) Self-absorption (0.1%) 3272400200011 (ERR-7) The momentum effects of fission nucleus recoil 3272400200012 induced by incident neutrons (0.2%) 3272400200013 (ERR-8,,0.1) Fission of other Pu isotopes (<0.1%) 3272400200014 (ERR-9,,0.1) Fission of other U isotopes (<0.1%) 3272400200015 STATUS (TABLE) Table 4 of Atom.Energy Sci.Tech.15(1981)12 3272400200016 ENDBIB 14 0 3272400200017 COMMON 7 6 3272400200018 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 3272400200019 ERR-7 3272400200020 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3272400200021 PER-CENT 3272400200022 1.5 1.0 0.9 0.2 1.4 0.13272400200023 0.2 3272400200024 ENDCOMMON 6 0 3272400200025 DATA 2 38 3272400200026 EN DATA 3272400200027 MEV NO-DIM 3272400200028 0.03 0.818 3272400200029 0.10 0.937 3272400200030 0.15 1.007 3272400200031 0.22 1.085 3272400200032 0.27 1.193 3272400200033 0.40 1.260 3272400200034 0.50 1.370 3272400200035 0.516 1.348 3272400200036 0.616 1.418 3272400200037 0.729 1.451 3272400200038 0.835 1.477 3272400200039 0.883 1.489 3272400200040 0.933 1.401 3272400200041 0.990 1.390 3272400200042 1.00 1.431 3272400200043 1.089 1.452 3272400200044 1.14 1.486 3272400200045 1.24 1.485 3272400200046 1.30 1.505 3272400200047 1.345 1.490 3272400200048 1.45 1.550 3272400200049 1.50 1.560 3272400200050 1.547 1.588 3272400200051 1.70 1.555 3272400200052 2.489 1.575 3272400200053 2.988 1.532 3272400200054 3.392 1.619 3272400200055 3.60 1.552 3272400200056 4.1 1.533 3272400200057 4.5 1.551 3272400200058 5.0 1.565 3272400200059 5.2 1.545 3272400200060 5.4 1.559 3272400200061 5.7 1.522 3272400200062 13.3 1.246 3272400200063 14.5 1.205 3272400200064 16.2 1.179 3272400200065 17.2 1.216 3272400200066 ENDDATA 40 0 3272400200067 ENDSUBENT 66 0 3272400299999 ENDENTRY 2 0 3272499999999