JEFF-3.1.1 General purpose neutron file update release Jan. 2009 2311 0 0 0 2.003000+3 2.989032+0 0 0 2 2 225 1451 1 0.000000+0 0.000000+0 0 0 0 6 225 1451 2 1.000000+0 2.000000+7 1 0 10 31 225 1451 3 0.000000+0 0.000000+0 0 0 177 8 225 1451 4 2-He- 3 LANL EVAL-MAY90 G.HALE, D.DODDER, P.YOUNG 225 1451 5 DIST-JAN09 20090105 225 1451 6 ----JEFF-311 MATERIAL 225 225 1451 7 -----INCIDENT NEUTRON DATA 225 1451 8 ------ENDF-6 FORMAT 225 1451 9 *************************** JEFF-3.1.1 ************************* 225 1451 10 ** ** 225 1451 11 ** Original data taken from: JEFF-3.1 ** 225 1451 12 ** ** 225 1451 13 ****************************************************************** 225 1451 14 ***************************** JEFF-3.1 ************************* 225 1451 15 ** ** 225 1451 16 ** Original data taken from: JEFF-3.0 ** 225 1451 17 ** ** 225 1451 18 ****************************************************************** 225 1451 19 225 1451 20 ***************************** JEFF-3.0 ************************* 225 1451 21 225 1451 22 DATA TAKEN FROM :- ENDF/B-VI.3 (DIST-SEP91 REV1-JUL91) 225 1451 23 225 1451 24 ****************************************************************** 225 1451 25 225 1451 26 MOD1 OF ENDF/B-VI 225 1451 27 225 1451 28 THE ONLY REVISION MADE FOR MOD1 OF ENDF/B-VI WAS TO ADD THE 225 1451 29 COMMENTS BELOW ON THE STANDARDS COVARIANCES. THE DESCRIPTION 225 1451 30 OF THE ENDF/B-VI EVALUATION IS GIVEN BELOW. 225 1451 31 225 1451 32 ***************************************************************** 225 1451 33 225 1451 34 ---------------------------------------------------------------- 225 1451 35 HE-3 FREE ATOM EVALUATION 225 1451 36 ENDF/B-VI DESCRIPTION 225 1451 37 ---------------------------------------------------------------- 225 1451 38 225 1451 39 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 225 1451 40 225 1451 41 this file transfered from l.stewart's endf/b-iii evaluation with 225 1451 42 modifications only in the 3he(n,p) and the elastic cross sections 225 1451 43 below 5 MeV, and the total cross section below 0.1 MeV. 225 1451 44 * * * * * * * 225 1451 45 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 225 1451 46 * * 225 1451 47 * cross section standard he-3 (n,p) * 225 1451 48 * * 225 1451 49 * the he-3 (n,p) cross section for this material is recommended 225 1451 50 * as a standard for neutron energies from thermal to 50 kev 225 1451 51 * * 225 1451 52 * * * * * * * 225 1451 53 225 1451 54 225 1451 55 mf=1 225 1451 56 225 1451 57 mt=451, atomic mass=3.0160 225 1451 58 225 1451 59 mf=2 225 1451 60 225 1451 61 mt=151, scattering length=0.2821e-12 cm. 225 1451 62 225 1451 63 mf=3 225 1451 64 225 1451 65 mt= 1, total cross sections --- from .00001 ev to 200 kev 225 1451 66 mt1 taken as sum mt2+mt102+mt103. from 200 kev to 20 225 1451 67 mev, mt1 evaluated using experimental data from ref.6. 225 1451 68 225 1451 69 mt= 2, elastic scattering cross sections --- from .00001 ev 225 1451 70 to 200 kev, mt2 taken approximately from r-matrix 225 1451 71 analysis described below. above 200 kev, obtained 225 1451 72 from mt2=mt1-mt102-mt103-mt104. note two reactions 225 1451 73 missing from this evaluation, namely n,n-prime,p and 225 1451 74 n,2n,2p. exp. data at 15 mev indicates non-zero 225 1451 75 cross sections for these. included in mt2 this eval. 225 1451 76 225 1451 77 mt=102, radiative capture cross sections --- thermal value 225 1451 78 taken from ref.17, with assumption of 1/v energy 225 1451 79 energy variation at all other energies. 225 1451 80 225 1451 81 mt=103, n-p cross sections --- below 5 mev taken from an 225 1451 82 r-matrix calculation of the four-body reactions 225 1451 83 by hale and dodder. 3he(n,p) data included were 225 1451 84 from refs. 5,13,14, and 15. for energies in the 225 1451 85 5-20 mev range, data were used as follows - 225 1451 86 ref.4 - 5.8 mev to 11. mev 225 1451 87 ref.10- 5.0 mev to 11. mev 225 1451 88 ref.12- 5.0 mev to 12. mev 225 1451 89 ref.16- 14. mev 225 1451 90 data extrapolated to 20. mev. 225 1451 91 225 1451 92 mt=104, n-d cross sections --- threshold=4.36147mev 225 1451 93 q=-3.2684 mev. evaluation from a detailed balance 225 1451 94 calculation(ref.13) and experimental data(ref.11). 225 1451 95 225 1451 96 mt=251, average value of cosine of elastic scattering angle, 225 1451 97 laboratory system. obtained from data mf=4,mt=2. 225 1451 98 225 1451 99 mt=252, values of xi, obtained from data mf=4,mt=2 225 1451 100 225 1451 101 mt=253, values of gamma,obtained from data mf=4,mt=2 225 1451 102 225 1451 103 mf=4 225 1451 104 225 1451 105 mt= 2, angular distribution of secondary neutrons from 225 1451 106 elastic scatter. evaluated from experimental data 225 1451 107 from refs.2,7,9,11,16,17 covering incident energies 225 1451 108 as follows - 225 1451 109 incident energy references 225 1451 110 1.e-5ev (isotropic) 225 1451 111 0.5 mev (isotropic) 225 1451 112 1.0 mev 9 225 1451 113 2.0 mev 9 225 1451 114 2.6 mev 11 225 1451 115 3.5 mev 9 225 1451 116 5.0 mev 11 225 1451 117 6.0 mev 9,7(from p+t elastic scatt) 225 1451 118 8.0 mev 11,7(from p+t elastic scatt) 225 1451 119 14.5 mev 16,17(from p+t elastic scatt) 225 1451 120 17.5 mev 11 225 1451 121 20.0 mev 2(from p+t elastic scatt) 225 1451 122 225 1451 123 references 225 1451 124 225 1451 125 1. r.batchelor,r.aves,and t.h.r.skyrme,rev.sci.instr.26,1037 225 1451 126 (1955). 225 1451 127 2. r.a.vanetsian and e.d.fenchenko,soviet journal of atomic 225 1451 128 energy 2,141(1957). 225 1451 129 3. j.n.bradbury and l.stewart,bull.am.phys.soc.3,417(1958) 225 1451 130 4. g.f.bogdanov,n.a.vlasov,c.p.kalinin,b.v.rybakov,l.n. 225 1451 131 samoilov,and v.a.sidorov,jetp(ussr)36,633(1959). 225 1451 132 5. j.h.gibbons and r.l.macklin,phys.rev.114,571(1959). 225 1451 133 6. los alamos physics and cryogenics groups,nucl.phys.12, 225 1451 134 291(1959). 225 1451 135 7. j.e.brolley,jr.,t.m.putnam,l.rosen,and l.stewart,phys. 225 1451 136 rev.159,777(1967). 225 1451 137 8. j.e.perry,private communication to stewart(1960) 225 1451 138 9. j.d.seagrave,l.cranberg,and j.e.simmons,phys.rev.119, 225 1451 139 1981(1960) 225 1451 140 10. m.d.goldberg,j.d.anderson,j.p.stoering,and c.wong,phys. 225 1451 141 rev.122,1510(1961). 225 1451 142 11. a.r.sayers,k.w.jones,and c.s.wu,phys.rev.122,1853(1961). 225 1451 143 12. w.e.wilson,r.l.walter,and d.b.fossan,nucl.phys.27,421 225 1451 144 (1961). 225 1451 145 13. j.als-nielsen and o.dietrich,phys.rev.133,b925(1964). 225 1451 146 14. r.l.macklin and j.h.gibbons,proceedings of the internatl. 225 1451 147 conf.on the study of nucl.struct.with neuts.,antwerp(1965) 225 1451 148 15. j.h.gibbons,private communication to stewart(1966). 225 1451 149 16. b.antolkovic,g.paic,p.tomas,and r.rendic,phys.rev.159, 225 1451 150 777(1967). 225 1451 151 17. l.rosen and w.leland,private communication(1967) 225 1451 152 18. s.mughabghab et al., neut.cross sect., vol.1, neut.reson. 225 1451 153 parameters and thermal cross sect., academic pr.(1981). 225 1451 154 225 1451 155 **************************************************************** 225 1451 156 225 1451 157 STANDARDS COVARIANCES 225 1451 158 225 1451 159 Phase 1 reviewers of the ENDF/B-VI standards cross sections have 225 1451 160 expressed the concern that the uncertainties resulting from the 225 1451 161 combination of R-matrix and simultaneous evaluations might have 225 1451 162 led to uncertainties that are too small. As a result, the 225 1451 163 Standards Subcommittee produced (at the May, 1990 CSEWG meeting) 225 1451 164 a set of expanded covariance estimates for the standard cross 225 1451 165 section reactions. These uncertainties are estimates such that 225 1451 166 if a modern day experiment were performed on a given standard 225 1451 167 cross section using the best techniques, approximately 2/3 of 225 1451 168 the results should fall within these expanded uncertainties. The 225 1451 169 expanded uncertainties for the He-3(n,p) cross section are as 225 1451 170 follows: 225 1451 171 225 1451 172 Energy Range Estimated Uncertainty 225 1451 173 (keV) (percent) 225 1451 174 225 1451 175 1.0E-08 - 0.1 0.3 225 1451 176 0.1 - 1.0 0.7 225 1451 177 1.0 - 10. 2.0 225 1451 178 10. - 50. 5.0 225 1451 179 **************************************************************** 225 1451 180 225 1451 181 1 451 189 0 225 1451 182 2 151 4 0 225 1451 183 3 1 41 0 225 1451 184 3 2 41 0 225 1451 185 3 102 4 0 225 1451 186 3 103 41 0 225 1451 187 3 104 13 0 225 1451 188 4 2 121 0 225 1451 189 0.000000+0 0.000000+0 0 0 0 0 225 1 099999 0.000000+0 0.000000+0 0 0 0 0 225 0 0 0 2.003000+3 2.989032+0 0 0 1 0 225 2151 1 2.003000+3 1.000000+0 0 0 1 0 225 2151 2 2.500000-2 1.000000+6 0 0 0 0 225 2151 3 5.000000-1 5.132265-1 0 0 0 0 225 2151 4 0.000000+0 0.000000+0 0 0 0 0 225 2 099999 0.000000+0 0.000000+0 0 0 0 0 225 0 0 0 2.003000+3 2.989032+0 0 0 0 0 225 3 1 1 0.000000+0 0.000000+0 0 0 1 113 225 3 1 2 113 5 225 3 1 3 1.000000-5 2.674533+5 1.000000-4 8.458122+4 1.000000-3 2.674754+4 225 3 1 4 1.000000-2 8.459482+3 2.530000-2 5.319310+3 1.000000-1 2.676610+3 225 3 1 5 1.000000+0 8.478401+2 1.000000+1 2.695200+2 1.000000+2 8.662700+1 225 3 1 6 2.000000+2 6.184549+1 4.000000+2 4.431541+1 6.000000+2 3.654586+1 225 3 1 7 8.000001+2 3.191384+1 1.000000+3 2.875200+1 1.400000+3 2.459745+1 225 3 1 8 2.000000+3 2.088962+1 2.400000+3 1.923328+1 3.000000+3 1.739609+1 225 3 1 9 4.000000+3 1.530827+1 5.000000+3 1.388252+1 6.000000+3 1.282876+1 225 3 1 10 7.000000+3 1.200986+1 8.000000+3 1.135054+1 9.000000+3 1.080456+1 225 3 1 11 1.000000+4 1.034260+1 1.200000+4 9.603198+0 1.500000+4 8.793340+0 225 3 1 12 1.700000+4 8.377701+0 2.000000+4 7.872085+0 2.200000+4 7.591327+0 225 3 1 13 2.500000+4 7.230230+0 2.700000+4 7.020152+0 3.000000+4 6.740128+0 225 3 1 14 3.200000+4 6.572285+0 3.500000+4 6.343189+0 4.000000+4 6.008800+0 225 3 1 15 4.500000+4 5.725154+0 5.000000+4 5.484613+0 5.500000+4 5.277510+0 225 3 1 16 6.000000+4 5.096862+0 6.500000+4 4.937501+0 7.000000+4 4.795692+0 225 3 1 17 7.500000+4 4.668419+0 8.000000+4 4.553445+0 9.000000+4 4.353676+0 225 3 1 18 1.000000+5 4.185600+0 1.200000+5 3.917828+0 1.400000+5 3.713688+0 225 3 1 19 1.600000+5 3.553070+0 1.800000+5 3.424107+0 2.000000+5 3.318700+0 225 3 1 20 2.500000+5 3.139142+0 3.000000+5 3.033722+0 3.500000+5 2.964101+0 225 3 1 21 4.000000+5 2.910000+0 4.500000+5 2.860000+0 5.000000+5 2.840000+0 225 3 1 22 5.500000+5 2.801129+0 6.000000+5 2.770000+0 6.500000+5 2.760075+0 225 3 1 23 7.000000+5 2.750000+0 7.500000+5 2.759234+0 8.000000+5 2.770000+0 225 3 1 24 8.500000+5 2.798433+0 9.000000+5 2.820000+0 9.500000+5 2.848147+0 225 3 1 25 1.000000+6 2.870000+0 1.100000+6 2.938605+0 1.200000+6 3.000000+0 225 3 1 26 1.300000+6 3.050000+0 1.400000+6 3.100000+0 1.500000+6 3.180000+0 225 3 1 27 1.600000+6 3.200000+0 1.700000+6 3.220000+0 1.800000+6 3.230000+0 225 3 1 28 1.900000+6 3.221922+0 2.000000+6 3.200000+0 2.200000+6 3.156421+0 225 3 1 29 2.400000+6 3.112286+0 2.500000+6 3.090609+0 2.600000+6 3.066519+0 225 3 1 30 2.800000+6 3.012724+0 3.000000+6 2.950000+0 3.500000+6 2.790000+0 225 3 1 31 4.000000+6 2.650000+0 4.362604+6 2.555441+0 4.380000+6 2.551113+0 225 3 1 32 4.500000+6 2.519700+0 5.000000+6 2.400000+0 5.500000+6 2.280000+0 225 3 1 33 6.000000+6 2.180000+0 6.500000+6 2.080200+0 7.000000+6 1.980500+0 225 3 1 34 7.500000+6 1.900200+0 8.000000+6 1.820100+0 8.500000+6 1.740000+0 225 3 1 35 9.000000+6 1.670000+0 9.500000+6 1.620500+0 1.000000+7 1.550500+0 225 3 1 36 1.050000+7 1.490400+0 1.100000+7 1.430000+0 1.150000+7 1.385500+0 225 3 1 37 1.200000+7 1.339800+0 1.250000+7 1.295500+0 1.300000+7 1.250100+0 225 3 1 38 1.350000+7 1.210100+0 1.400000+7 1.170000+0 1.500000+7 1.112000+0 225 3 1 39 1.600000+7 1.050000+0 1.700000+7 9.920000-1 1.800000+7 9.400000-1 225 3 1 40 1.900000+7 8.930000-1 2.000000+7 8.510000-1 225 3 1 41 0.000000+0 0.000000+0 0 0 0 0 225 3 099999 2.003000+3 2.989032+0 0 0 0 0 225 3 2 1 0.000000+0 0.000000+0 0 0 1 113 225 3 2 2 113 5 225 3 2 3 1.000000-5 3.310000+0 1.000000-4 3.310000+0 1.000000-3 3.310000+0 225 3 2 4 1.000000-2 3.310000+0 2.530000-2 3.310000+0 1.000000-1 3.310000+0 225 3 2 5 1.000000+0 3.310000+0 1.000000+1 3.300000+0 1.000000+2 3.270000+0 225 3 2 6 2.000000+2 3.255489+0 4.000000+2 3.234405+0 6.000000+2 3.219862+0 225 3 2 7 8.000001+2 3.208842+0 1.000000+3 3.200000+0 1.400000+3 3.182527+0 225 3 2 8 2.000000+3 3.156624+0 2.400000+3 3.141110+0 3.000000+3 3.120556+0 225 3 2 9 4.000000+3 3.092272+0 5.000000+3 3.069556+0 6.000000+3 3.050856+0 225 3 2 10 7.000000+3 3.035147+0 8.000000+3 3.021736+0 9.000000+3 3.010137+0 225 3 2 11 1.000000+4 3.000000+0 1.200000+4 2.986929+0 1.500000+4 2.977040+0 225 3 2 12 1.700000+4 2.971037+0 2.000000+4 2.959285+0 2.200000+4 2.948968+0 225 3 2 13 2.500000+4 2.929630+0 2.700000+4 2.914316+0 3.000000+4 2.888128+0 225 3 2 14 3.200000+4 2.868787+0 3.500000+4 2.837389+0 4.000000+4 2.780000+0 225 3 2 15 4.500000+4 2.723954+0 5.000000+4 2.674613+0 5.500000+4 2.630642+0 225 3 2 16 6.000000+4 2.591062+0 6.500000+4 2.555136+0 7.000000+4 2.522292+0 225 3 2 17 7.500000+4 2.492082+0 8.000000+4 2.464145+0 9.000000+4 2.413976+0 225 3 2 18 1.000000+5 2.370000+0 1.200000+5 2.295728+0 1.400000+5 2.234688+0 225 3 2 19 1.600000+5 2.183170+0 1.800000+5 2.138807+0 2.000000+5 2.100000+0 225 3 2 20 2.500000+5 2.032242+0 3.000000+5 1.989522+0 3.500000+5 1.955601+0 225 3 2 21 4.000000+5 1.924030+0 4.500000+5 1.891840+0 5.000000+5 1.889440+0 225 3 2 22 5.500000+5 1.869615+0 6.000000+5 1.857660+0 6.500000+5 1.866566+0 225 3 2 23 7.000000+5 1.873720+0 7.500000+5 1.897052+0 8.000000+5 1.919340+0 225 3 2 24 8.500000+5 1.955621+0 9.000000+5 1.981500+0 9.500000+5 2.011556+0 225 3 2 25 1.000000+6 2.031610+0 1.100000+6 2.090898+0 1.200000+6 2.141000+0 225 3 2 26 1.300000+6 2.178650+0 1.400000+6 2.219360+0 1.500000+6 2.294960+0 225 3 2 27 1.600000+6 2.316150+0 1.700000+6 2.342730+0 1.800000+6 2.364030+0 225 3 2 28 1.900000+6 2.371119+0 2.000000+6 2.367020+0 2.200000+6 2.364501+0 225 3 2 29 2.400000+6 2.364376+0 2.500000+6 2.364785+0 2.600000+6 2.362459+0 225 3 2 30 2.800000+6 2.350674+0 3.000000+6 2.327310+0 3.500000+6 2.252490+0 225 3 2 31 4.000000+6 2.179640+0 4.362604+6 2.124213+0 4.380000+6 2.120612+0 225 3 2 32 4.500000+6 2.099110+0 5.000000+6 2.010000+0 5.500000+6 1.913000+0 225 3 2 33 6.000000+6 1.834000+0 6.500000+6 1.754000+0 7.000000+6 1.666000+0 225 3 2 34 7.500000+6 1.599000+0 8.000000+6 1.532000+0 8.500000+6 1.462900+0 225 3 2 35 9.000000+6 1.403000+0 9.500000+6 1.364000+0 1.000000+7 1.302000+0 225 3 2 36 1.050000+7 1.251000+0 1.100000+7 1.197000+0 1.150000+7 1.160000+0 225 3 2 37 1.200000+7 1.121000+0 1.250000+7 1.082500+0 1.300000+7 1.043000+0 225 3 2 38 1.350000+7 1.008000+0 1.400000+7 9.719000-1 1.500000+7 9.240000-1 225 3 2 39 1.600000+7 8.718000-1 1.700000+7 8.234000-1 1.800000+7 7.819000-1 225 3 2 40 1.900000+7 7.450000-1 2.000000+7 7.130000-1 225 3 2 41 0.000000+0 0.000000+0 0 0 0 0 225 3 099999 2.003000+3 2.989032+0 0 0 0 0 225 3102 1 2.057778+7 2.057778+7 0 0 1 3 225 3102 2 3 5 225 3102 3 1.000000-5 1.559272-3 2.530000-2 3.100000-5 2.000000+7 1.102572-9 225 3102 4 0.000000+0 0.000000+0 0 0 0 0 225 3 099999 2.003000+3 2.989032+0 0 0 0 0 225 3103 1 7.637520+5 7.637520+5 0 0 1 113 225 3103 2 113 5 225 3103 3 1.000000-5 2.674500+5 1.000000-4 8.457790+4 1.000000-3 2.674423+4 225 3103 4 1.000000-2 8.456170+3 2.530000-2 5.316000+3 1.000000-1 2.673300+3 225 3103 5 1.000000+0 8.445301+2 1.000000+1 2.662200+2 1.000000+2 8.335700+1 225 3103 6 2.000000+2 5.859000+1 4.000000+2 4.108100+1 6.000000+2 3.332600+1 225 3103 7 8.000001+2 2.870500+1 1.000000+3 2.555200+1 1.400000+3 2.141492+1 225 3103 8 2.000000+3 1.773300+1 2.400000+3 1.609217+1 3.000000+3 1.427553+1 225 3103 9 4.000000+3 1.221600+1 5.000000+3 1.081296+1 6.000000+3 9.777900+0 225 3103 10 7.000000+3 8.974711+0 8.000000+3 8.328800+0 9.000000+3 7.794425+0 225 3103 11 1.000000+4 7.342600+0 1.200000+4 6.616269+0 1.500000+4 5.816300+0 225 3103 12 1.700000+4 5.406664+0 2.000000+4 4.912800+0 2.200000+4 4.642359+0 225 3103 13 2.500000+4 4.300600+0 2.700000+4 4.105836+0 3.000000+4 3.852000+0 225 3103 14 3.200000+4 3.703498+0 3.500000+4 3.505800+0 4.000000+4 3.228800+0 225 3103 15 4.500000+4 3.001200+0 5.000000+4 2.810000+0 5.500000+4 2.646868+0 225 3103 16 6.000000+4 2.505800+0 6.500000+4 2.382365+0 7.000000+4 2.273400+0 225 3103 17 7.500000+4 2.176337+0 8.000000+4 2.089300+0 9.000000+4 1.939700+0 225 3103 18 1.000000+5 1.815600+0 1.200000+5 1.622100+0 1.400000+5 1.479000+0 225 3103 19 1.600000+5 1.369900+0 1.800000+5 1.285300+0 2.000000+5 1.218700+0 225 3103 20 2.500000+5 1.106900+0 3.000000+5 1.044200+0 3.500000+5 1.008500+0 225 3103 21 4.000000+5 9.859700-1 4.500000+5 9.681600-1 5.000000+5 9.505600-1 225 3103 22 5.500000+5 9.315136-1 6.000000+5 9.123400-1 6.500000+5 8.935094-1 225 3103 23 7.000000+5 8.762800-1 7.500000+5 8.621818-1 8.000000+5 8.506600-1 225 3103 24 8.500000+5 8.428116-1 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