1 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 19 7 225 1451 3 0.000000+0 0.000000+0 0 0 174 2 225 1451 4 2-He- 3 LANL EVAL-MAY90 G.Hale, D.Dodder, P.Young 225 1451 5 DIST-DEC06 225 1451 6 ----INTERN. STANDARD MATERIAL 225 225 1451 7 -----STANDARDS SUBLIBRARY 225 1451 8 ------ENDF-6 FORMAT 225 1451 9 225 1451 10 ***************************************************************** 225 1451 11 225 1451 12 3He(n,p) section of the ENDF/B-VII standards 225 1451 13 sub-library submitted by A.D. Carlson, NIST on 28 February 2006. 225 1451 14 This evaluation is carried over directly from ENDF/B-VI. 225 1451 15 This cross section is recommended as a standard below 50 keV. 225 1451 16 225 1451 17 ***************************************************************** 225 1451 18 225 1451 19 ENDF/B-VII CONVERTED FROM ENDF/B-VI BY NNDC OCT 2004 225 1451 20 225 1451 21 ***************************************************************** 225 1451 22 225 1451 23 MOD1 OF ENDF/B-VI 225 1451 24 225 1451 25 THE ONLY REVISION MADE FOR MOD1 OF ENDF/B-VI WAS TO ADD THE 225 1451 26 COMMENTS BELOW ON THE STANDARDS COVARIANCES. THE DESCRIPTION 225 1451 27 OF THE ENDF/B-VI EVALUATION IS GIVEN BELOW. 225 1451 28 225 1451 29 ***************************************************************** 225 1451 30 225 1451 31 ---------------------------------------------------------------- 225 1451 32 HE-3 FREE ATOM EVALUATION 225 1451 33 ENDF/B-VI DESCRIPTION 225 1451 34 ---------------------------------------------------------------- 225 1451 35 225 1451 36 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 225 1451 37 225 1451 38 this file transfered from l.stewart's endf/b-iii evaluation with 225 1451 39 modifications only in the 3he(n,p) and the elastic cross sections 225 1451 40 below 5 MeV, and the total cross section below 0.1 MeV. 225 1451 41 * * * * * * * 225 1451 42 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 225 1451 43 * * 225 1451 44 * cross section standard he-3 (n,p) * 225 1451 45 * * 225 1451 46 * the he-3 (n,p) cross section for this material is recommended 225 1451 47 * as a standard for neutron energies from thermal to 50 kev 225 1451 48 * * 225 1451 49 * * * * * * * 225 1451 50 225 1451 51 225 1451 52 mf=1 225 1451 53 225 1451 54 mt=451, atomic mass=3.0160 225 1451 55 225 1451 56 mf=2 225 1451 57 225 1451 58 mt=151, scattering length=0.2821e-12 cm. 225 1451 59 225 1451 60 mf=3 225 1451 61 225 1451 62 mt= 1, total cross sections --- from .00001 ev to 200 kev 225 1451 63 mt1 taken as sum mt2+mt102+mt103. from 200 kev to 20 225 1451 64 mev, mt1 evaluated using experimental data from ref.6. 225 1451 65 225 1451 66 mt= 2, elastic scattering cross sections --- from .00001 ev 225 1451 67 to 200 kev, mt2 taken approximately from r-matrix 225 1451 68 analysis described below. above 200 kev, obtained 225 1451 69 from mt2=mt1-mt102-mt103-mt104. note two reactions 225 1451 70 missing from this evaluation, namely n,n-prime,p and 225 1451 71 n,2n,2p. exp. data at 15 mev indicates non-zero 225 1451 72 cross sections for these. included in mt2 this eval. 225 1451 73 225 1451 74 mt=102, radiative capture cross sections --- thermal value 225 1451 75 taken from ref.17, with assumption of 1/v energy 225 1451 76 energy variation at all other energies. 225 1451 77 225 1451 78 mt=103, n-p cross sections --- below 5 mev taken from an 225 1451 79 r-matrix calculation of the four-body reactions 225 1451 80 by hale and dodder. 3he(n,p) data included were 225 1451 81 from refs. 5,13,14, and 15. for energies in the 225 1451 82 5-20 mev range, data were used as follows - 225 1451 83 ref.4 - 5.8 mev to 11. mev 225 1451 84 ref.10- 5.0 mev to 11. mev 225 1451 85 ref.12- 5.0 mev to 12. mev 225 1451 86 ref.16- 14. mev 225 1451 87 data extrapolated to 20. mev. 225 1451 88 225 1451 89 mt=104, n-d cross sections --- threshold=4.36147mev 225 1451 90 q=-3.2684 mev. evaluation from a detailed balance 225 1451 91 calculation(ref.13) and experimental data(ref.11). 225 1451 92 225 1451 93 mt=251, average value of cosine of elastic scattering angle, 225 1451 94 laboratory system. obtained from data mf=4,mt=2. 225 1451 95 225 1451 96 mt=252, values of xi, obtained from data mf=4,mt=2 225 1451 97 225 1451 98 mt=253, values of gamma,obtained from data mf=4,mt=2 225 1451 99 225 1451 100 mf=4 225 1451 101 225 1451 102 mt= 2, angular distribution of secondary neutrons from 225 1451 103 elastic scatter. evaluated from experimental data 225 1451 104 from refs.2,7,9,11,16,17 covering incident energies 225 1451 105 as follows - 225 1451 106 incident energy references 225 1451 107 1.e-5ev (isotropic) 225 1451 108 0.5 mev (isotropic) 225 1451 109 1.0 mev 9 225 1451 110 2.0 mev 9 225 1451 111 2.6 mev 11 225 1451 112 3.5 mev 9 225 1451 113 5.0 mev 11 225 1451 114 6.0 mev 9,7(from p+t elastic scatt) 225 1451 115 8.0 mev 11,7(from p+t elastic scatt) 225 1451 116 14.5 mev 16,17(from p+t elastic scatt) 225 1451 117 17.5 mev 11 225 1451 118 20.0 mev 2(from p+t elastic scatt) 225 1451 119 225 1451 120 references 225 1451 121 225 1451 122 1. r.batchelor,r.aves,and t.h.r.skyrme,rev.sci.instr.26,1037 225 1451 123 (1955). 225 1451 124 2. r.a.vanetsian and e.d.fenchenko,soviet journal of atomic 225 1451 125 energy 2,141(1957). 225 1451 126 3. j.n.bradbury and l.stewart,bull.am.phys.soc.3,417(1958) 225 1451 127 4. g.f.bogdanov,n.a.vlasov,c.p.kalinin,b.v.rybakov,l.n. 225 1451 128 samoilov,and v.a.sidorov,jetp(ussr)36,633(1959). 225 1451 129 5. j.h.gibbons and r.l.macklin,phys.rev.114,571(1959). 225 1451 130 6. los alamos physics and cryogenics groups,nucl.phys.12, 225 1451 131 291(1959). 225 1451 132 7. j.e.brolley,jr.,t.m.putnam,l.rosen,and l.stewart,phys. 225 1451 133 rev.159,777(1967). 225 1451 134 8. j.e.perry,private communication to stewart(1960) 225 1451 135 9. j.d.seagrave,l.cranberg,and j.e.simmons,phys.rev.119, 225 1451 136 1981(1960) 225 1451 137 10. m.d.goldberg,j.d.anderson,j.p.stoering,and c.wong,phys. 225 1451 138 rev.122,1510(1961). 225 1451 139 11. a.r.sayers,k.w.jones,and c.s.wu,phys.rev.122,1853(1961). 225 1451 140 12. w.e.wilson,r.l.walter,and d.b.fossan,nucl.phys.27,421 225 1451 141 (1961). 225 1451 142 13. j.als-nielsen and o.dietrich,phys.rev.133,b925(1964). 225 1451 143 14. r.l.macklin and j.h.gibbons,proceedings of the internatl. 225 1451 144 conf.on the study of nucl.struct.with neuts.,antwerp(1965) 225 1451 145 15. j.h.gibbons,private communication to stewart(1966). 225 1451 146 16. b.antolkovic,g.paic,p.tomas,and r.rendic,phys.rev.159, 225 1451 147 777(1967). 225 1451 148 17. l.rosen and w.leland,private communication(1967) 225 1451 149 18. s.mughabghab et al., neut.cross sect., vol.1, neut.reson. 225 1451 150 parameters and thermal cross sect., academic pr.(1981). 225 1451 151 225 1451 152 **************************************************************** 225 1451 153 225 1451 154 STANDARDS COVARIANCES 225 1451 155 225 1451 156 Phase 1 reviewers of the ENDF/B-VI standards cross sections have 225 1451 157 expressed the concern that the uncertainties resulting from the 225 1451 158 combination of R-matrix and simultaneous evaluations might have 225 1451 159 led to uncertainties that are too small. As a result, the 225 1451 160 Standards Subcommittee produced (at the May, 1990 CSEWG meeting) 225 1451 161 a set of expanded covariance estimates for the standard cross 225 1451 162 section reactions. These uncertainties are estimates such that 225 1451 163 if a modern day experiment were performed on a given standard 225 1451 164 cross section using the best techniques, approximately 2/3 of 225 1451 165 the results should fall within these expanded uncertainties. The 225 1451 166 expanded uncertainties for the He-3(n,p) cross section are as 225 1451 167 follows: 225 1451 168 225 1451 169 Energy Range Estimated Uncertainty 225 1451 170 (keV) (percent) 225 1451 171 225 1451 172 1.0E-08 - 0.1 0.3 225 1451 173 0.1 - 1.0 0.7 225 1451 174 1.0 - 10. 2.0 225 1451 175 10. - 50. 5.0 225 1451 176 225 1451 177 ****************************** CONTENTS ************************** 225 1451 178 1 451 180 0 225 1451 179 3 103 41 0 225 1451 180 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 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 9.000000+5 8.385000-1 9.500000+5 8.365911-1 225 3103 25 1.000000+6 8.383900-1 1.100000+6 8.477074-1 1.200000+6 8.590000-1 225 3103 26 1.300000+6 8.713500-1 1.400000+6 8.806400-1 1.500000+6 8.850400-1 225 3103 27 1.600000+6 8.838500-1 1.700000+6 8.772700-1 1.800000+6 8.659700-1 225 3103 28 1.900000+6 8.508025-1 2.000000+6 8.329800-1 2.200000+6 7.919200-1 225 3103 29 2.400000+6 7.479100-1 2.500000+6 7.258239-1 2.600000+6 7.040600-1 225 3103 30 2.800000+6 6.620500-1 3.000000+6 6.226900-1 3.500000+6 5.375100-1 225 3103 31 4.000000+6 4.703600-1 4.362604+6 4.312280-1 4.380000+6 4.295011-1 225 3103 32 4.500000+6 4.178900-1 5.000000+6 3.720000-1 5.500000+6 3.340000-1 225 3103 33 6.000000+6 3.030000-1 6.500000+6 2.750000-1 7.000000+6 2.570000-1 225 3103 34 7.500000+6 2.390000-1 8.000000+6 2.220000-1 8.500000+6 2.080000-1 225 3103 35 9.000000+6 1.960000-1 9.500000+6 1.840000-1 1.000000+7 1.750000-1 225 3103 36 1.050000+7 1.650000-1 1.100000+7 1.580000-1 1.150000+7 1.500000-1 225 3103 37 1.200000+7 1.430000-1 1.250000+7 1.370000-1 1.300000+7 1.310000-1 225 3103 38 1.350000+7 1.260000-1 1.400000+7 1.220000-1 1.500000+7 1.120000-1 225 3103 39 1.600000+7 1.040000-1 1.700000+7 9.760000-2 1.800000+7 9.180000-2 225 3103 40 1.900000+7 8.660000-2 2.000000+7 8.200000-2 225 3103 41 0.000000+0 0.000000+0 0 0 0 0 225 3 099999 0.000000+0 0.000000+0 0 0 0 0 225 0 0 0 0.000000+0 0.000000+0 0 0 0 0 0 0 0 0 -1 0 0 0