$Rev:: 532 $ $Date:: 2011-12-05#$ 1 0 0 0 2.003000+3 2.989032+0 0 0 0 0 225 1451 1 0.000000+0 0.000000+0 0 0 0 6 225 1451 2 1.000000+0 2.000000+7 1 0 10 7 225 1451 3 0.000000+0 0.000000+0 0 0 184 8 225 1451 4 2-He- 3 LANL EVAL-MAY90 G.Hale,D.Dodder,P.Young 225 1451 5 DIST-DEC06 20111222 225 1451 6 ----ENDF/B-VII.1 MATERIAL 225 225 1451 7 -----INCIDENT NEUTRON DATA 225 1451 8 ------ENDF-6 FORMAT 225 1451 9 225 1451 10 225 1451 11 **************************************************************** 225 1451 12 ENDF/B-VII.1 225 1451 13 **************************************************************** 225 1451 14 225 1451 15 New capture cross sections were evaluated with the EDA code. 225 1451 16 The ENDF/B-VI evaluation is strictly 1/v, going through a low 225 1451 17 thermal value, whereas the data indicate a higher thermal value, 225 1451 18 and resonance structure around 2 MeV. This fit also had data in 225 1451 19 the 4He(gamma,n) direction that indicated a much higher cross 225 1451 20 section in the MeV region, and that is the reason why the new 225 1451 21 evaluation looks overshooting the experimental 3He(n,g) data 225 1451 22 in the MeV region. The differences in the new and old capture 225 1451 23 cross sections was added to the total cross sections. 225 1451 24 225 1451 25 G. Hale (Apr. 2011) 225 1451 26 225 1451 27 **************************************************************** 225 1451 28 225 1451 29 ENDF/B-VII CONVERTED FROM ENDF/B-VI BY NNDC OCT 2004 225 1451 30 225 1451 31 **************************************************************** 225 1451 32 225 1451 33 MOD1 OF ENDF/B-VI 225 1451 34 225 1451 35 THE ONLY REVISION MADE FOR MOD1 OF ENDF/B-VI WAS TO ADD THE 225 1451 36 COMMENTS BELOW ON THE STANDARDS COVARIANCES. THE DESCRIPTION 225 1451 37 OF THE ENDF/B-VI EVALUATION IS GIVEN BELOW. 225 1451 38 225 1451 39 ***************************************************************** 225 1451 40 225 1451 41 ---------------------------------------------------------------- 225 1451 42 HE-3 FREE ATOM EVALUATION 225 1451 43 ENDF/B-VI DESCRIPTION 225 1451 44 ---------------------------------------------------------------- 225 1451 45 225 1451 46 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 225 1451 47 225 1451 48 this file transfered from l.stewart's endf/b-iii evaluation with 225 1451 49 modifications only in the 3he(n,p) and the elastic cross sections 225 1451 50 below 5 MeV, and the total cross section below 0.1 MeV. 225 1451 51 * * * * * * * 225 1451 52 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 225 1451 53 * * 225 1451 54 * cross section standard he-3 (n,p) * 225 1451 55 * * 225 1451 56 * the he-3 (n,p) cross section for this material is recommended 225 1451 57 * as a standard for neutron energies from thermal to 50 kev 225 1451 58 * * 225 1451 59 * * * * * * * 225 1451 60 225 1451 61 225 1451 62 mf=1 225 1451 63 225 1451 64 mt=451, atomic mass=3.0160 225 1451 65 225 1451 66 mf=2 225 1451 67 225 1451 68 mt=151, scattering length=0.2821e-12 cm. 225 1451 69 225 1451 70 mf=3 225 1451 71 225 1451 72 mt= 1, total cross sections --- from .00001 ev to 200 kev 225 1451 73 mt1 taken as sum mt2+mt102+mt103. from 200 kev to 20 225 1451 74 mev, mt1 evaluated using experimental data from ref.6. 225 1451 75 225 1451 76 mt= 2, elastic scattering cross sections --- from .00001 ev 225 1451 77 to 200 kev, mt2 taken approximately from r-matrix 225 1451 78 analysis described below. above 200 kev, obtained 225 1451 79 from mt2=mt1-mt102-mt103-mt104. note two reactions 225 1451 80 missing from this evaluation, namely n,n-prime,p and 225 1451 81 n,2n,2p. exp. data at 15 mev indicates non-zero 225 1451 82 cross sections for these. included in mt2 this eval. 225 1451 83 225 1451 84 mt=102, radiative capture cross sections --- thermal value 225 1451 85 taken from ref.17, with assumption of 1/v energy 225 1451 86 energy variation at all other energies. 225 1451 87 225 1451 88 mt=103, n-p cross sections --- below 5 mev taken from an 225 1451 89 r-matrix calculation of the four-body reactions 225 1451 90 by hale and dodder. 3he(n,p) data included were 225 1451 91 from refs. 5,13,14, and 15. for energies in the 225 1451 92 5-20 mev range, data were used as follows - 225 1451 93 ref.4 - 5.8 mev to 11. mev 225 1451 94 ref.10- 5.0 mev to 11. mev 225 1451 95 ref.12- 5.0 mev to 12. mev 225 1451 96 ref.16- 14. mev 225 1451 97 data extrapolated to 20. mev. 225 1451 98 225 1451 99 mt=104, n-d cross sections --- threshold=4.36147mev 225 1451 100 q=-3.2684 mev. evaluation from a detailed balance 225 1451 101 calculation(ref.13) and experimental data(ref.11). 225 1451 102 225 1451 103 mt=251, average value of cosine of elastic scattering angle, 225 1451 104 laboratory system. obtained from data mf=4,mt=2. 225 1451 105 225 1451 106 mt=252, values of xi, obtained from data mf=4,mt=2 225 1451 107 225 1451 108 mt=253, values of gamma,obtained from data mf=4,mt=2 225 1451 109 225 1451 110 mf=4 225 1451 111 225 1451 112 mt= 2, angular distribution of secondary neutrons from 225 1451 113 elastic scatter. evaluated from experimental data 225 1451 114 from refs.2,7,9,11,16,17 covering incident energies 225 1451 115 as follows - 225 1451 116 incident energy references 225 1451 117 1.e-5ev (isotropic) 225 1451 118 0.5 mev (isotropic) 225 1451 119 1.0 mev 9 225 1451 120 2.0 mev 9 225 1451 121 2.6 mev 11 225 1451 122 3.5 mev 9 225 1451 123 5.0 mev 11 225 1451 124 6.0 mev 9,7(from p+t elastic scatt) 225 1451 125 8.0 mev 11,7(from p+t elastic scatt) 225 1451 126 14.5 mev 16,17(from p+t elastic scatt) 225 1451 127 17.5 mev 11 225 1451 128 20.0 mev 2(from p+t elastic scatt) 225 1451 129 225 1451 130 references 225 1451 131 225 1451 132 1. r.batchelor,r.aves,and t.h.r.skyrme,rev.sci.instr.26,1037 225 1451 133 (1955). 225 1451 134 2. r.a.vanetsian and e.d.fenchenko,soviet journal of atomic 225 1451 135 energy 2,141(1957). 225 1451 136 3. j.n.bradbury and l.stewart,bull.am.phys.soc.3,417(1958) 225 1451 137 4. g.f.bogdanov,n.a.vlasov,c.p.kalinin,b.v.rybakov,l.n. 225 1451 138 samoilov,and v.a.sidorov,jetp(ussr)36,633(1959). 225 1451 139 5. j.h.gibbons and r.l.macklin,phys.rev.114,571(1959). 225 1451 140 6. los alamos physics and cryogenics groups,nucl.phys.12, 225 1451 141 291(1959). 225 1451 142 7. j.e.brolley,jr.,t.m.putnam,l.rosen,and l.stewart,phys. 225 1451 143 rev.159,777(1967). 225 1451 144 8. j.e.perry,private communication to stewart(1960) 225 1451 145 9. j.d.seagrave,l.cranberg,and j.e.simmons,phys.rev.119, 225 1451 146 1981(1960) 225 1451 147 10. m.d.goldberg,j.d.anderson,j.p.stoering,and c.wong,phys. 225 1451 148 rev.122,1510(1961). 225 1451 149 11. a.r.sayers,k.w.jones,and c.s.wu,phys.rev.122,1853(1961). 225 1451 150 12. w.e.wilson,r.l.walter,and d.b.fossan,nucl.phys.27,421 225 1451 151 (1961). 225 1451 152 13. j.als-nielsen and o.dietrich,phys.rev.133,b925(1964). 225 1451 153 14. r.l.macklin and j.h.gibbons,proceedings of the internatl. 225 1451 154 conf.on the study of nucl.struct.with neuts.,antwerp(1965) 225 1451 155 15. j.h.gibbons,private communication to stewart(1966). 225 1451 156 16. b.antolkovic,g.paic,p.tomas,and r.rendic,phys.rev.159, 225 1451 157 777(1967). 225 1451 158 17. l.rosen and w.leland,private communication(1967) 225 1451 159 18. s.mughabghab et al., neut.cross sect., vol.1, neut.reson. 225 1451 160 parameters and thermal cross sect., academic pr.(1981). 225 1451 161 225 1451 162 **************************************************************** 225 1451 163 225 1451 164 STANDARDS COVARIANCES 225 1451 165 225 1451 166 Phase 1 reviewers of the ENDF/B-VI standards cross sections have 225 1451 167 expressed the concern that the uncertainties resulting from the 225 1451 168 combination of R-matrix and simultaneous evaluations might have 225 1451 169 led to uncertainties that are too small. As a result, the 225 1451 170 Standards Subcommittee produced (at the May, 1990 CSEWG meeting) 225 1451 171 a set of expanded covariance estimates for the standard cross 225 1451 172 section reactions. These uncertainties are estimates such that 225 1451 173 if a modern day experiment were performed on a given standard 225 1451 174 cross section using the best techniques, approximately 2/3 of 225 1451 175 the results should fall within these expanded uncertainties. The 225 1451 176 expanded uncertainties for the He-3(n,p) cross section are as 225 1451 177 follows: 225 1451 178 225 1451 179 Energy Range Estimated Uncertainty 225 1451 180 (keV) (percent) 225 1451 181 225 1451 182 1.0E-08 - 0.1 0.3 225 1451 183 0.1 - 1.0 0.7 225 1451 184 1.0 - 10. 2.0 225 1451 185 10. - 50. 5.0 225 1451 186 **************************************************************** 225 1451 187 225 1451 188 1 451 196 0 225 1451 189 2 151 4 0 225 1451 190 3 1 43 0 225 1451 191 3 2 41 0 225 1451 192 3 102 23 0 225 1451 193 3 103 41 0 225 1451 194 3 104 13 0 225 1451 195 4 2 100 0 225 1451 196 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 1 118 225 3 1 2 118 2 225 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 2.000000+0 6.004605+2 5.000000+0 3.805577+2 225 3 1 6 1.000000+1 2.695200+2 2.000000+1 1.915146+2 5.000000+1 1.219108+2 225 3 1 7 1.000000+2 8.662700+1 2.000000+2 6.184549+1 4.000000+2 4.431541+1 225 3 1 8 5.000000+2 3.985495+1 6.000000+2 3.654586+1 8.000001+2 3.191384+1 225 3 1 9 1.000000+3 2.875200+1 1.400000+3 2.459745+1 2.000000+3 2.088962+1 225 3 1 10 2.400000+3 1.923328+1 3.000000+3 1.739609+1 4.000000+3 1.530827+1 225 3 1 11 5.000000+3 1.388253+1 6.000000+3 1.282877+1 7.000000+3 1.200987+1 225 3 1 12 8.000000+3 1.135055+1 9.000000+3 1.080457+1 1.000000+4 1.034261+1 225 3 1 13 1.200000+4 9.603206+0 1.500000+4 8.793349+0 1.700000+4 8.377710+0 225 3 1 14 2.000000+4 7.872095+0 2.200000+4 7.591337+0 2.500000+4 7.230241+0 225 3 1 15 2.700000+4 7.020163+0 3.000000+4 6.740140+0 3.200000+4 6.572297+0 225 3 1 16 3.500000+4 6.343202+0 4.000000+4 6.008814+0 4.500000+4 5.725169+0 225 3 1 17 5.000000+4 5.484629+0 5.500000+4 5.277527+0 6.000000+4 5.096879+0 225 3 1 18 6.500000+4 4.937519+0 7.000000+4 4.795711+0 7.500000+4 4.668438+0 225 3 1 19 8.000000+4 4.553465+0 9.000000+4 4.353697+0 1.000000+5 4.185623+0 225 3 1 20 1.200000+5 3.917853+0 1.400000+5 3.713714+0 1.600000+5 3.553098+0 225 3 1 21 1.800000+5 3.424137+0 2.000000+5 3.318732+0 2.500000+5 3.139178+0 225 3 1 22 3.000000+5 3.033762+0 3.500000+5 2.964144+0 4.000000+5 2.910046+0 225 3 1 23 4.500000+5 2.860049+0 5.000000+5 2.840052+0 5.500000+5 2.801183+0 225 3 1 24 6.000000+5 2.770057+0 6.500000+5 2.760134+0 7.000000+5 2.750061+0 225 3 1 25 7.500000+5 2.759298+0 8.000000+5 2.770066+0 8.500000+5 2.798501+0 225 3 1 26 9.000000+5 2.820070+0 9.500000+5 2.848219+0 1.000000+6 2.870074+0 225 3 1 27 1.100000+6 2.938682+0 1.200000+6 3.000080+0 1.300000+6 3.050083+0 225 3 1 28 1.400000+6 3.100085+0 1.500000+6 3.180087+0 1.600000+6 3.200089+0 225 3 1 29 1.700000+6 3.220091+0 1.800000+6 3.230092+0 1.900000+6 3.222015+0 225 3 1 30 2.000000+6 3.200094+0 2.200000+6 3.156515+0 2.400000+6 3.112380+0 225 3 1 31 2.500000+6 3.090702+0 2.600000+6 3.066612+0 2.800000+6 3.012815+0 225 3 1 32 3.000000+6 2.950089+0 3.500000+6 2.790082+0 4.000000+6 2.650076+0 225 3 1 33 4.362604+6 2.555513+0 4.380000+6 2.551184+0 4.500000+6 2.519770+0 225 3 1 34 5.000000+6 2.400065+0 5.500000+6 2.280061+0 6.000000+6 2.180056+0 225 3 1 35 6.500000+6 2.080253+0 7.000000+6 1.980551+0 7.500000+6 1.900248+0 225 3 1 36 8.000000+6 1.820146+0 8.500000+6 1.740045+0 9.000000+6 1.670043+0 225 3 1 37 9.500000+6 1.620542+0 1.000000+7 1.550541+0 1.050000+7 1.490440+0 225 3 1 38 1.100000+7 1.430039+0 1.150000+7 1.385538+0 1.200000+7 1.339837+0 225 3 1 39 1.250000+7 1.295537+0 1.300000+7 1.250136+0 1.350000+7 1.210135+0 225 3 1 40 1.400000+7 1.170035+0 1.500000+7 1.112034+0 1.600000+7 1.050033+0 225 3 1 41 1.700000+7 9.920318-1 1.800000+7 9.400307-1 1.900000+7 8.930297-1 225 3 1 42 2.000000+7 8.510286-1 225 3 1 43 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 2 60 225 3102 2 10 5 60 2 225 3102 3 1.000000-5 2.764700-3 1.000000-4 8.742800-4 1.000000-3 2.764700-4 225 3102 4 1.000000-2 8.743000-5 2.530000-2 5.498000-5 1.000000-1 2.767000-5 225 3102 5 1.000000+0 8.813814-6 2.000000+0 6.282554-6 5.000000+0 4.068773-6 225 3102 6 1.000000+1 2.989414-6 2.000000+1 2.272732-6 5.000000+1 1.738891-6 225 3102 7 1.000000+2 1.584892-6 2.000000+2 1.623177-6 5.000000+2 1.980015-6 225 3102 8 1.000000+3 2.523756-6 2.000000+3 3.373808-6 5.000000+3 5.149799-6 225 3102 9 1.000000+4 7.197366-6 2.000000+4 1.012000-5 5.000000+4 1.597000-5 225 3102 10 1.000000+5 2.262000-5 2.000000+5 3.214000-5 3.000000+5 3.957000-5 225 3102 11 4.000000+5 4.592000-5 5.000000+5 5.158000-5 6.000000+5 5.672000-5 225 3102 12 7.000000+5 6.145000-5 8.000000+5 6.581000-5 9.000000+5 6.984000-5 225 3102 13 1.000000+6 7.355000-5 1.200000+6 8.004000-5 1.400000+6 8.527000-5 225 3102 14 1.600000+6 8.924000-5 1.800000+6 9.198000-5 2.000000+6 9.356000-5 225 3102 15 2.200000+6 9.409000-5 2.400000+6 9.371000-5 2.600000+6 9.260000-5 225 3102 16 2.800000+6 9.090000-5 3.000000+6 8.879000-5 3.500000+6 8.250000-5 225 3102 17 4.000000+6 7.591000-5 4.500000+6 6.985000-5 5.000000+6 6.461000-5 225 3102 18 6.000000+6 5.641000-5 7.000000+6 5.058000-5 8.000000+6 4.635000-5 225 3102 19 9.000000+6 4.318000-5 1.000000+7 4.073000-5 1.100000+7 3.880000-5 225 3102 20 1.200000+7 3.725000-5 1.300000+7 3.594000-5 1.400000+7 3.480000-5 225 3102 21 1.500000+7 3.375000-5 1.600000+7 3.275000-5 1.700000+7 3.176000-5 225 3102 22 1.800000+7 3.075000-5 1.900000+7 2.971000-5 2.000000+7 2.862000-5 225 3102 23 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 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