JEFF-3.3_Incident_Neutron_File 1 0 0 0 2003.00000 2.99012000 0 0 2 0 225 1451 1 0.0 0.0 0 0 0 6 225 1451 2 1.00000000 20000000.0 3 0 10 3 225 1451 3 0.0 0.0 0 0 187 8 225 1451 4 2-He- 3 LANL EVAL-MAY90 G.Hale,D.Dodder,P.Young 225 1451 5 DIST-DEC17 REV3-DEC17 20171231 225 1451 6 ---JEFF-3.3 MATERIAL 225 225 1451 7 -----INCIDENT NEUTRON DATA 225 1451 8 ------ENDF-6 FORMAT 225 1451 9 ***************************** JEFF-3.2 *********************** 225 1451 10 225 1451 11 *****C. Jouanne (Dec. 2015) corrections on Mass and Q reac 225 1451 12 **************************************************************** 225 1451 13 ENDF/B-VII.1 225 1451 14 **************************************************************** 225 1451 15 225 1451 16 New capture cross sections were evaluated with the EDA code. 225 1451 17 The ENDF/B-VI evaluation is strictly 1/v, going through a low 225 1451 18 thermal value, whereas the data indicate a higher thermal value, 225 1451 19 and resonance structure around 2 MeV. This fit also had data in 225 1451 20 the 4He(gamma,n) direction that indicated a much higher cross 225 1451 21 section in the MeV region, and that is the reason why the new 225 1451 22 evaluation looks overshooting the experimental 3He(n,g) data 225 1451 23 in the MeV region. The differences in the new and old capture 225 1451 24 cross sections was added to the total cross sections. 225 1451 25 225 1451 26 G. Hale (Apr. 2011) 225 1451 27 225 1451 28 **************************************************************** 225 1451 29 225 1451 30 ENDF/B-VII CONVERTED FROM ENDF/B-VI BY NNDC OCT 2004 225 1451 31 225 1451 32 **************************************************************** 225 1451 33 225 1451 34 MOD1 OF ENDF/B-VI 225 1451 35 225 1451 36 THE ONLY REVISION MADE FOR MOD1 OF ENDF/B-VI WAS TO ADD THE 225 1451 37 COMMENTS BELOW ON THE STANDARDS COVARIANCES. THE DESCRIPTION 225 1451 38 OF THE ENDF/B-VI EVALUATION IS GIVEN BELOW. 225 1451 39 225 1451 40 ***************************************************************** 225 1451 41 225 1451 42 ---------------------------------------------------------------- 225 1451 43 HE-3 FREE ATOM EVALUATION 225 1451 44 ENDF/B-VI DESCRIPTION 225 1451 45 ---------------------------------------------------------------- 225 1451 46 225 1451 47 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 225 1451 48 225 1451 49 this file transfered from l.stewart's endf/b-iii evaluation with 225 1451 50 modifications only in the 3he(n,p) and the elastic cross sections 225 1451 51 below 5 MeV, and the total cross section below 0.1 MeV. 225 1451 52 * * * * * * * 225 1451 53 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 225 1451 54 * * 225 1451 55 * cross section standard he-3 (n,p) * 225 1451 56 * * 225 1451 57 * the he-3 (n,p) cross section for this material is recommended 225 1451 58 * as a standard for neutron energies from thermal to 50 kev 225 1451 59 * * 225 1451 60 * * * * * * * 225 1451 61 225 1451 62 225 1451 63 mf=1 225 1451 64 225 1451 65 mt=451, atomic mass=3.0160 225 1451 66 225 1451 67 mf=2 225 1451 68 225 1451 69 mt=151, scattering length=0.2821e-12 cm. 225 1451 70 225 1451 71 mf=3 225 1451 72 225 1451 73 mt= 1, total cross sections --- from .00001 ev to 200 kev 225 1451 74 mt1 taken as sum mt2+mt102+mt103. from 200 kev to 20 225 1451 75 mev, mt1 evaluated using experimental data from ref.6. 225 1451 76 225 1451 77 mt= 2, elastic scattering cross sections --- from .00001 ev 225 1451 78 to 200 kev, mt2 taken approximately from r-matrix 225 1451 79 analysis described below. above 200 kev, obtained 225 1451 80 from mt2=mt1-mt102-mt103-mt104. note two reactions 225 1451 81 missing from this evaluation, namely n,n-prime,p and 225 1451 82 n,2n,2p. exp. data at 15 mev indicates non-zero 225 1451 83 cross sections for these. included in mt2 this eval. 225 1451 84 225 1451 85 mt=102, radiative capture cross sections --- thermal value 225 1451 86 taken from ref.17, with assumption of 1/v energy 225 1451 87 energy variation at all other energies. 225 1451 88 225 1451 89 mt=103, n-p cross sections --- below 5 mev taken from an 225 1451 90 r-matrix calculation of the four-body reactions 225 1451 91 by hale and dodder. 3he(n,p) data included were 225 1451 92 from refs. 5,13,14, and 15. for energies in the 225 1451 93 5-20 mev range, data were used as follows - 225 1451 94 ref.4 - 5.8 mev to 11. mev 225 1451 95 ref.10- 5.0 mev to 11. mev 225 1451 96 ref.12- 5.0 mev to 12. mev 225 1451 97 ref.16- 14. mev 225 1451 98 data extrapolated to 20. mev. 225 1451 99 225 1451 100 mt=104, n-d cross sections --- threshold=4.36147mev 225 1451 101 q=-3.2684 mev. evaluation from a detailed balance 225 1451 102 calculation(ref.13) and experimental data(ref.11). 225 1451 103 225 1451 104 mt=251, average value of cosine of elastic scattering angle, 225 1451 105 laboratory system. obtained from data mf=4,mt=2. 225 1451 106 225 1451 107 mt=252, values of xi, obtained from data mf=4,mt=2 225 1451 108 225 1451 109 mt=253, values of gamma,obtained from data mf=4,mt=2 225 1451 110 225 1451 111 mf=4 225 1451 112 225 1451 113 mt= 2, angular distribution of secondary neutrons from 225 1451 114 elastic scatter. evaluated from experimental data 225 1451 115 from refs.2,7,9,11,16,17 covering incident energies 225 1451 116 as follows - 225 1451 117 incident energy references 225 1451 118 1.e-5ev (isotropic) 225 1451 119 0.5 mev (isotropic) 225 1451 120 1.0 mev 9 225 1451 121 2.0 mev 9 225 1451 122 2.6 mev 11 225 1451 123 3.5 mev 9 225 1451 124 5.0 mev 11 225 1451 125 6.0 mev 9,7(from p+t elastic scatt) 225 1451 126 8.0 mev 11,7(from p+t elastic scatt) 225 1451 127 14.5 mev 16,17(from p+t elastic scatt) 225 1451 128 17.5 mev 11 225 1451 129 20.0 mev 2(from p+t elastic scatt) 225 1451 130 225 1451 131 references 225 1451 132 225 1451 133 1. r.batchelor,r.aves,and t.h.r.skyrme,rev.sci.instr.26,1037 225 1451 134 (1955). 225 1451 135 2. r.a.vanetsian and e.d.fenchenko,soviet journal of atomic 225 1451 136 energy 2,141(1957). 225 1451 137 3. j.n.bradbury and l.stewart,bull.am.phys.soc.3,417(1958) 225 1451 138 4. g.f.bogdanov,n.a.vlasov,c.p.kalinin,b.v.rybakov,l.n. 225 1451 139 samoilov,and v.a.sidorov,jetp(ussr)36,633(1959). 225 1451 140 5. j.h.gibbons and r.l.macklin,phys.rev.114,571(1959). 225 1451 141 6. los alamos physics and cryogenics groups,nucl.phys.12, 225 1451 142 291(1959). 225 1451 143 7. j.e.brolley,jr.,t.m.putnam,l.rosen,and l.stewart,phys. 225 1451 144 rev.159,777(1967). 225 1451 145 8. j.e.perry,private communication to stewart(1960) 225 1451 146 9. j.d.seagrave,l.cranberg,and j.e.simmons,phys.rev.119, 225 1451 147 1981(1960) 225 1451 148 10. m.d.goldberg,j.d.anderson,j.p.stoering,and c.wong,phys. 225 1451 149 rev.122,1510(1961). 225 1451 150 11. a.r.sayers,k.w.jones,and c.s.wu,phys.rev.122,1853(1961). 225 1451 151 12. w.e.wilson,r.l.walter,and d.b.fossan,nucl.phys.27,421 225 1451 152 (1961). 225 1451 153 13. j.als-nielsen and o.dietrich,phys.rev.133,b925(1964). 225 1451 154 14. r.l.macklin and j.h.gibbons,proceedings of the internatl. 225 1451 155 conf.on the study of nucl.struct.with neuts.,antwerp(1965) 225 1451 156 15. j.h.gibbons,private communication to stewart(1966). 225 1451 157 16. b.antolkovic,g.paic,p.tomas,and r.rendic,phys.rev.159, 225 1451 158 777(1967). 225 1451 159 17. l.rosen and w.leland,private communication(1967) 225 1451 160 18. s.mughabghab et al., neut.cross sect., vol.1, neut.reson. 225 1451 161 parameters and thermal cross sect., academic pr.(1981). 225 1451 162 225 1451 163 **************************************************************** 225 1451 164 225 1451 165 STANDARDS COVARIANCES 225 1451 166 225 1451 167 Phase 1 reviewers of the ENDF/B-VI standards cross sections have 225 1451 168 expressed the concern that the uncertainties resulting from the 225 1451 169 combination of R-matrix and simultaneous evaluations might have 225 1451 170 led to uncertainties that are too small. As a result, the 225 1451 171 Standards Subcommittee produced (at the May, 1990 CSEWG meeting) 225 1451 172 a set of expanded covariance estimates for the standard cross 225 1451 173 section reactions. These uncertainties are estimates such that 225 1451 174 if a modern day experiment were performed on a given standard 225 1451 175 cross section using the best techniques, approximately 2/3 of 225 1451 176 the results should fall within these expanded uncertainties. The 225 1451 177 expanded uncertainties for the He-3(n,p) cross section are as 225 1451 178 follows: 225 1451 179 225 1451 180 Energy Range Estimated Uncertainty 225 1451 181 (keV) (percent) 225 1451 182 225 1451 183 1.0E-08 - 0.1 0.3 225 1451 184 0.1 - 1.0 0.7 225 1451 185 1.0 - 10. 2.0 225 1451 186 10. - 50. 5.0 225 1451 187 **************************************************************** 225 1451 188 225 1451 189 ***************** Program ENDF2C (Version 2017-1) *************** 225 1451 190 Convert ENDF Data to Standard FORTRAN, C and C++ Format 225 1451 191 1 451 197 0 225 1451 192 2 151 4 0 225 1451 193 3 1 43 0 225 1451 194 3 2 41 0 225 1451 195 3 102 23 0 225 1451 196 3 103 41 0 225 1451 197 3 104 13 0 225 1451 198 4 2 100 0 225 1451 199 225 1 099999 225 0 0 0 2003.00000 2.99012000 0 0 1 0 225 2151 1 2003.00000 1.00000000 0 0 1 0 225 2151 2 .025000000 1000000.00 0 0 0 0 225 2151 3 .500000000 .513226500 0 0 0 0 225 2151 4 225 2 099999 225 0 0 0 2003.00000 2.99012000 0 0 0 0 225 3 1 1 0.0 0.0 0 0 1 118 225 3 1 2 118 2 225 3 1 3 1.00000E-5 267453.300 1.00000E-4 84581.2200 .001000000 26747.5400 225 3 1 4 .010000000 8459.48200 .025300000 5319.31000 .100000000 2676.61000 225 3 1 5 1.00000000 847.840100 2.00000000 600.460500 5.00000000 380.557700 225 3 1 6 10.0000000 269.520000 20.0000000 191.514600 50.0000000 121.910800 225 3 1 7 100.000000 86.6270000 200.000000 61.8454900 400.000000 44.3154100 225 3 1 8 500.000000 39.8549500 600.000000 36.5458600 800.000100 31.9138400 225 3 1 9 1000.00000 28.7520000 1400.00000 24.5974500 2000.00000 20.8896200 225 3 1 10 2400.00000 19.2332800 3000.00000 17.3960900 4000.00000 15.3082700 225 3 1 11 5000.00000 13.8825300 6000.00000 12.8287700 7000.00000 12.0098700 225 3 1 12 8000.00000 11.3505500 9000.00000 10.8045700 10000.0000 10.3426100 225 3 1 13 12000.0000 9.60320600 15000.0000 8.79334900 17000.0000 8.37771000 225 3 1 14 20000.0000 7.87209500 22000.0000 7.59133700 25000.0000 7.23024100 225 3 1 15 27000.0000 7.02016300 30000.0000 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