ENTRY 23280 20230324 231623280 0 1 SUBENT 23280001 20230324 231623280 1 1 BIB 16 99 23280 1 2 TITLE Neutron induced fission cross sections of 242Pu from 23280 1 3 0.3 MeV to 3 MeV. 23280 1 4 AUTHOR (P.Salvador-Castineira,T.Brys,R.Eykens,F.-J.Hambsch, 23280 1 5 A.Goeoek, A.Moens, S.Oberstedt, G.Sibbens,D.Vanleeuw, 23280 1 6 M.Vidali, C.Pretel) 23280 1 7 INSTITUTE (2ZZZGEL) P.Salvador-Castineira,T.Brys,R.Eykens, 23280 1 8 F.-J.Hambsch,A.Goeoek,A.Moens,S.Oberstedt,G.Sibbens, 23280 1 9 D.Vanleeuw,M.Vidali. 23280 1 10 (2SPNUPC) P.Salvador-Castineira,C.Pretel 23280 1 11 REFERENCE (J,PR/C,92,044606,2015) 23280 1 12 #doi:10.1103/PhysRevC.92.044606 23280 1 13 Main reference. Pu-242 data on Figures. 23280 1 14 (J,PPRC,64,177,2015) Initial publication. 23280 1 15 #doi:10.1016/j.phpro.2015.04.024 23280 1 16 Figures for Pu-240,-242, U-238, Np-237 fission C-S. 23280 1 17 (J,NDS,119,38,2014) First author F.-J.Hambsch . 23280 1 18 Preliminary Pu242 CS on Fig.4 . 23280 1 19 (J,NDS,119,55,2014) Prelim.publication on figures. 23280 1 20 (J,PPRC,47,150,2013) Prelim.publication on figures. 23280 1 21 REL-REF (I,,P.Salvador-Castineira+,J,PR/C,92,014620,2015) 23280 1 22 Exp. details. Pu-240 c-s measurement. Entry 23281. 23280 1 23 FACILITY (VDG,2ZZZGEL) Van de Graaff accelerator at IRMM. 23280 1 24 INC-SOURCE (P-LI7) for neutrons 0.3 - 1.8 MeV 23280 1 25 (P-T) for neutrons of 1.6 - 3.0 MeV. 23280 1 26 INC-SPECT Quasimonoenergetic neutrons. 23280 1 27 DETECTOR (FISCH) Twin Frisch-grid ionization chamber TFGIC for 23280 1 28 fission fragments detection. 23280 1 29 Digital signal processing (DSP) code developed at 23280 1 30 JRC-IRMM was used. 23280 1 31 Paraffin-B4C layer shielding of the TFGIC was used at 23280 1 32 measurement relative to U235(n,f) to avoid neutrons 23280 1 33 scattered in the target hall. 23280 1 34 SAMPLE Pu-242 sample and reference sample ( Np237,U235,U238) 23280 1 35 were placed in TFGIC cathode holder in back-to-back 23280 1 36 geometry. 23280 1 37 Pu-242 sample was produced by electrodeposition on Al 23280 1 38 backing, reference samples - by vacuum deposition on 23280 1 39 stainless steel( Np,U235) or transparent (U-238) - 23280 1 40 by the target preparation group at JRC-IRMM. 23280 1 41 242Pu 23280 1 42 Isotope mass,microg 671(0.9%) 23280 1 43 Diameter,mm 30(0.1%) 23280 1 44 Density,microg/cm2 95.3(0.8%) 23280 1 45 Alpha activity 0.0984MBq(0.3%) 23280 1 46 Content 238Pu 0.0027%, 239Pu 0.0044%, 23280 1 47 240Pu 0.0192%, 241Pu 0.0081% 23280 1 48 242Pu 99.9652%, 244Pu 0.0004% 23280 1 49 237Np 23280 1 50 Isotope mass,microg 390(0.3%) 23280 1 51 Diameter,mm 12.7 23280 1 52 Density,microg/cm2 308(0.3%) 23280 1 53 Alpha activity 0.001MBq(0.1%) 23280 1 54 Content,% 237Np 99.8%, 238Pu 0.2% 23280 1 55 235U 23280 1 56 Isotope mass,microg 584(2%) 23280 1 57 Diameter,mm 28 23280 1 58 Density,microg/cm2 94.8(2%) 23280 1 59 Alpha activity 265.7Bq(2%), with contribution of23280 1 60 the 234U and 235U isotopes 23280 1 61 Content 235U 99.5%, 234U 0.2%, 23280 1 62 236U 0.03%, 238U 0.3% 23280 1 63 238U 23280 1 64 Isotope mass,microg 577(0.4%) 23280 1 65 Diameter,mm 30 23280 1 66 Density,microg/cm2 81.7(0.4%) 23280 1 67 Alpha activity 7Bq(0.5%) 23280 1 68 Content 238U 99.99%, 234U <0.02% 23280 1 69 METHOD (PHD) Pulse high distributions. 23280 1 70 Ratios of fission cross sections were measured: 23280 1 71 Pu-242/Np-237, 23280 1 72 Pu-242/U-238 ( renormalized by using U-238/U-235 ), 23280 1 73 Pu-242/U-235 . 23280 1 74 MONITOR (92-U-235(N,F),,SIG) Primary standard 23280 1 75 MONIT-REF (,A.D.Carlson+,J,NDS,110,3215,2009) 23280 1 76 (,,3,ENDF/B-VII.1,,2011) 23280 1 77 CORRECTION Loss of fission events due to the electronic threshold.23280 1 78 Counts due to spontaneous fission: 23280 1 79 spon.fis.rate of Pu242 was ~0.5 fis/s, spont.fission 23280 1 80 half-life of Pu-242 T1/2,SF = 6.74E+10 yr (1.3%) . 23280 1 81 Self-absorption and geometrical efficiency. 23280 1 82 Neutron spectrum, sample inhomogeneity and solid angle.23280 1 83 Corrections due to the excited state of the 7Li(p,n)7Be23280 1 84 reaction. 23280 1 85 Due to the down-scattered neutrons. 23280 1 86 The neutron background was studied by means of MCNP 23280 1 87 simulations. 23280 1 88 ERR-ANALYS (ERR-S) Statistical 0.5% 23280 1 89 (ERR-1,,1.3) Counts SF <1.3% 23280 1 90 (ERR-2) 242Pu mass 0.9% 23280 1 91 (ERR-4,1.5,2.) 235U mass 1.5%-2% 23280 1 92 (ERR-6) Efficiency 1% 23280 1 93 (ERR-7) Sample purity 0.001% 23280 1 94 (ERR-8,,0.2) Correction of neutron spectrum <0.2% 23280 1 95 (ERR-9) MCNP correction of thermalized flux (ratio) 23280 1 96 (ERR-10,,0.8) 235U standard <0.8% 23280 1 97 (ERR-T) Total uncertainty 23280 1 98 HISTORY (20151226C) M.M. Data request was sent 17.03.2016 23280 1 99 (20160401R) Data were received from F.-K.Hambsch 23280 1 100 (20230324U) SD: Ref. PPRC,47,150 added. 23280 1 101 ENDBIB 99 0 23280 1 102 COMMON 5 3 23280 1 103 ERR-S ERR-2 ERR-6 ERR-7 ERR-9 23280 1 104 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23280 1 105 0.5 0.9 1. 0.001 0.5 23280 1 106 ENDCOMMON 3 0 23280 1 107 ENDSUBENT 106 0 23280 199999 SUBENT 23280002 20151226 224823280 2 1 BIB 4 7 23280 2 2 REACTION (94-PU-242(N,F),,SIG) 23280 2 3 MONITOR (93-NP-237(N,F),,SIG) 23280 2 4 Secondary standard. Benchmarked using U235(n,f). 23280 2 5 ERR-ANALYS (ERR-11,2.2,4.) 237Np ENDF evaluation 2.2% to 4%. 23280 2 6 (ERR-3) 237Np mass 0.3% 23280 2 7 STATUS (TABLE) From author 23280 2 8 Data are on Fig.4 of PR/C,92,044606,2015 23280 2 9 ENDBIB 7 0 23280 2 10 COMMON 1 3 23280 2 11 ERR-3 23280 2 12 PER-CENT 23280 2 13 0.3 23280 2 14 ENDCOMMON 3 0 23280 2 15 DATA 4 22 23280 2 16 EN EN-ERR DATA ERR-T 23280 2 17 MEV MEV B B 23280 2 18 0.30000 0.046500 0.06417410 0.003834887 23280 2 19 0.50000 0.040000 0.2251655 0.01061927 23280 2 20 0.69900 0.037000 0.5695855 0.03267098 23280 2 21 0.80000 0.035500 0.8309445 0.04083389 23280 2 22 0.90000 0.034500 1.076297 0.04775567 23280 2 23 0.90000 0.018000 1.096402 0.05372997 23280 2 24 0.95000 0.023000 1.235936 0.04942618 23280 2 25 1.00000 0.021500 1.214303 0.04984309 23280 2 26 1.00000 0.017500 1.309000 0.05406962 23280 2 27 1.05000 0.020500 1.349414 0.05019186 23280 2 28 1.10000 0.032000 1.376400 0.05007414 23280 2 29 1.10000 0.021000 1.360379 0.04941637 23280 2 30 1.15000 0.021500 1.377182 0.05077958 23280 2 31 1.20000 0.031000 1.385690 0.05075696 23280 2 32 1.30000 0.030500 1.318403 0.04484475 23280 2 33 1.40000 0.019000 1.333769 0.04747260 23280 2 34 1.50000 0.028500 1.335821 0.04416400 23280 2 35 1.60000 0.028000 1.347550 0.04453932 23280 2 36 1.60000 0.014500 1.341191 0.05729537 23280 2 37 1.60000 0.036000 1.343099 0.04399508 23280 2 38 1.70000 0.027500 1.331369 0.04426081 23280 2 39 1.80000 0.027000 1.343947 0.04468351 23280 2 40 ENDDATA 24 0 23280 2 41 ENDSUBENT 40 0 23280 299999 SUBENT 23280003 20151226 224823280 3 1 BIB 4 7 23280 3 2 REACTION (94-PU-242(N,F),,SIG) 23280 3 3 MONITOR (92-U-238(N,F),,SIG) 23280 3 4 Secondary standard. Benchmarked using U235(n,f). 23280 3 5 ERR-ANALYS (ERR-12) 238U standard 0.7% 23280 3 6 (ERR-5) 238U mass 0.5% 23280 3 7 STATUS (TABLE) From author 23280 3 8 Data are on Fig.4 of PR/C,92,044606,2015 23280 3 9 ENDBIB 7 0 23280 3 10 COMMON 2 3 23280 3 11 ERR-12 ERR-5 23280 3 12 PER-CENT PER-CENT 23280 3 13 0.7 0.5 23280 3 14 ENDCOMMON 3 0 23280 3 15 DATA 4 10 23280 3 16 EN EN-ERR DATA ERR-T 23280 3 17 MEV MEV B B 23280 3 18 1.600000 0.08700000 1.334361 0.03324959 23280 3 19 1.700000 0.08500000 1.341442 0.03375137 23280 3 20 1.800000 0.08250000 1.354618 0.03474807 23280 3 21 1.900000 0.08000000 1.391845 0.03586983 23280 3 22 2.000000 0.07800000 1.420137 0.03713207 23280 3 23 2.200000 0.07400000 1.377791 0.03614947 23280 3 24 2.400000 0.07100000 1.385526 0.03685876 23280 3 25 2.600000 0.06800000 1.424230 0.03818007 23280 3 26 2.800000 0.06500000 1.434743 0.03851673 23280 3 27 3.000000 0.06250000 1.468687 0.04443340 23280 3 28 ENDDATA 12 0 23280 3 29 ENDSUBENT 28 0 23280 399999 SUBENT 23280004 20151226 224823280 4 1 BIB 2 3 23280 4 2 REACTION (94-PU-242(N,F),,SIG) 23280 4 3 STATUS (TABLE) From author 23280 4 4 Data are on Fig.4 of PR/C,92,044606,2015 23280 4 5 ENDBIB 3 0 23280 4 6 NOCOMMON 0 0 23280 4 7 DATA 4 9 23280 4 8 EN EN-ERR DATA ERR-T 23280 4 9 MEV MEV B B 23280 4 10 0.500000 0.05400000 0.2389925 0.004821599 23280 4 11 0.900000 0.04600000 1.079022 0.02276572 23280 4 12 1.100000 0.04300000 1.385913 0.02808228 23280 4 13 1.500000 0.03800000 1.375719 0.02693880 23280 4 14 1.800000 0.03600000 1.406194 0.02848322 23280 4 15 1.800000 0.09000000 1.460394 0.02782387 23280 4 16 2.000000 0.08500000 1.499299 0.02896204 23280 4 17 2.500000 0.07500000 1.458655 0.02829045 23280 4 18 2.800000 0.07100000 1.464287 0.02862846 23280 4 19 ENDDATA 11 0 23280 4 20 ENDSUBENT 19 0 23280 499999 SUBENT 23280005 20151226 224823280 5 1 BIB 3 8 23280 5 2 REACTION (94-PU-242(N,F),,SIG) 23280 5 3 ANALYSIS Weighted average was calculated for all subsets of 23280 5 4 data. 23280 5 5 STATUS (TABLE) From author 23280 5 6 Data are on Fig.5 of PR/C,92,044606,2015 23280 5 7 (DEP,23280002) Measurement relative to Np-237 23280 5 8 (DEP,23280003) Measurement relative to U-238 23280 5 9 (DEP,23280004) Measurement relative to U-235 23280 5 10 ENDBIB 8 0 23280 5 11 NOCOMMON 0 0 23280 5 12 DATA 4 25 23280 5 13 EN EN-ERR DATA ERR-T 23280 5 14 MEV MEV B B 23280 5 15 0.3000000 0.04650000 0.06400000 0.003000000 23280 5 16 0.5000000 0.05400000 0.2370690 0.01000000 23280 5 17 0.6990000 0.03700000 0.5700000 0.03000000 23280 5 18 0.8000000 0.03550000 0.8090000 0.04000000 23280 5 19 0.9000000 0.04600000 1.080397 0.05000000 23280 5 20 0.9500000 0.02300000 1.236000 0.04000000 23280 5 21 1.000000 0.01750000 1.309000 0.05000000 23280 5 22 1.050000 0.02050000 1.349000 0.05000000 23280 5 23 1.100000 0.04300000 1.380255 0.05000000 23280 5 24 1.150000 0.02150000 1.377000 0.05000000 23280 5 25 1.200000 0.03100000 1.386000 0.05000000 23280 5 26 1.300000 0.03050000 1.318000 0.04000000 23280 5 27 1.400000 0.02900000 1.334000 0.04000000 23280 5 28 1.500000 0.03800000 1.368000 0.04000000 23280 5 29 1.600000 0.08700000 1.340220 0.05000000 23280 5 30 1.700000 0.08500000 1.337400 0.04000000 23280 5 31 1.800000 0.09000000 1.411876 0.04000000 23280 5 32 1.900000 0.08000000 1.452923 0.03000000 23280 5 33 2.000000 0.08500000 1.474692 0.03000000 23280 5 34 2.200000 0.07400000 1.459000 0.03000000 23280 5 35 2.400000 0.07100000 1.442077 0.03000000 23280 5 36 2.500000 0.07500000 1.432000 0.02000000 23280 5 37 2.600000 0.06800000 1.448231 0.03000000 23280 5 38 2.800000 0.07100000 1.455077 0.03000000 23280 5 39 3.000000 0.06250000 1.465000 0.04000000 23280 5 40 ENDDATA 27 0 23280 5 41 ENDSUBENT 40 0 23280 599999 ENDENTRY 5 0 2328099999999