endf/b-v tape 511 (standards materials) 511 0 0 0 2.00300+ 3 2.99010+ 0 0 0 0 11146 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 01146 1451 2 0.00000+ 0 0.00000+ 0 0 0 128 101146 1451 3 2-he- 30lasl eval-jun68 leona stewart (lasl) 1146 1451 4 no publication dist-may79 rev0 781116 1146 1451 5 1146 1451 6 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 1146 1451 7 1146 1451 8 this file transfered from endf/b-iii with no modifications. 1146 1451 9 * * * * * * *1146 1451 10 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *1146 1451 11 * *1146 1451 12 * cross section standard he-3 (n,p) *1146 1451 13 * *1146 1451 14 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *1146 1451 15 * *1146 1451 16 * the he-3 (n,p) cross section for this material is recommended 1146 1451 17 * *1146 1451 18 * as a standard for neutron energies from thermal to 50 kev 1146 1451 19 * *1146 1451 20 * * * * * * *1146 1451 21 1146 1451 22 helium-3 from an unpublished evaluation by l.stewart (lasl-1968)1146 1451 23 1146 1451 24 this evaluation of he-3 was recommended by the standards 1146 1451 25 subcommittee (csewg) for inclusion in endf/b at the oct. 1970 1146 1451 26 meeting of csewg. 1146 1451 27 1146 1451 28 data converted to endf/b format by m.drake(bnl) and r.labauve 1146 1451 29 (lasl) aug1971. 1146 1451 30 1146 1451 31 mf=1 1146 1451 32 1146 1451 33 mt=451, atomic mass=3.0160 1146 1451 34 1146 1451 35 mf=2 1146 1451 36 1146 1451 37 mt=151, scattering length=0.2821e-12 cm. 1146 1451 38 1146 1451 39 mf=3 1146 1451 40 1146 1451 41 mt= 1, total cross sections --- from .00001 ev to 10.8 kev 1146 1451 42 mt1 taken as sum mt2 + mt103. from 10.8 kev to 20.0 1146 1451 43 mev mt1 evaluated using experimental data from ref.6. 1146 1451 44 1146 1451 45 mt= 2, elastic scattering cross sections --- from .00001 ev 1146 1451 46 to 10.8 kev mt2 taken as constant=1.0 b. from 10.8 1146 1451 47 kev to 20.0 mev mt2=mt1-mt103-mt104 with experimental 1146 1451 48 data from ref.9 and 11 as check. note two reactions 1146 1451 49 missing from this evaluation, namely n,n-prime,p and 1146 1451 50 n,2n,2p. exp. data at 15.0mev indicates non-zero 1146 1451 51 cross sections for these. included in mt2 this eval. 1146 1451 52 1146 1451 53 mt=103, n-p cross sections --- from .00001 ev to 1.42 kev 1146 1451 54 mt103 taken as one-over-v(5327b at .0253ev)from 1146 1451 55 ref.13. from 1.42kev to 20.0mev mt 103 is evaluated 1146 1451 56 using experimental data from refs.1,4,5,8,10,11,12, 1146 1451 57 14,15,16 covering energy ranges as follows - 1146 1451 58 ref.1 - .12 mev to 1.2 mev 1146 1451 59 ref.4 - 5.8 mev to 11. mev 1146 1451 60 ref.5 - 5.0 kev to 4.2 mev 1146 1451 61 ref.8 - .48 mev to 4.5 mev 1146 1451 62 ref.10- 3.1 mev to 11. mev 1146 1451 63 ref.11- .95 mev 1146 1451 64 ref.12- 4.0 mev to 12. mev 1146 1451 65 ref.14- 5.0 kev to 4.2 mev 1146 1451 66 ref.15- 5.0 kev to 4.2 mev 1146 1451 67 ref.16- 14. mev 1146 1451 68 data extrapolated to 20.mev. 1146 1451 69 1146 1451 70 mt=104, n-d cross sections --- threshold=4.36147mev 1146 1451 71 q=-3.2684 mev. evaluation from a detailed balance 1146 1451 72 calculation(ref.13) and experimental data(ref.11). 1146 1451 73 1146 1451 74 mt=251, average value of cosine of elastic scattering angle, 1146 1451 75 laboratory system. obtained from data mf=4,mt=2. 1146 1451 76 1146 1451 77 mt=252, values of xi, obtained from data mf=4,mt=2 1146 1451 78 1146 1451 79 mt=253, values of gamma,obtained from data mf=4,mt=2 1146 1451 80 1146 1451 81 mf=4 1146 1451 82 1146 1451 83 mt= 2, angular distribution of secondary neutrons from 1146 1451 84 elastic scatter. evaluated from experimental data 1146 1451 85 from refs.2,7,9,11,16,17 covering incident energies 1146 1451 86 as follows - 1146 1451 87 incident energy references 1146 1451 88 1.e-5ev (isotropic) 1146 1451 89 0.5 mev (isotropic) 1146 1451 90 1.0 mev 9 1146 1451 91 2.0 mev 9 1146 1451 92 2.6 mev 11 1146 1451 93 3.5 mev 9 1146 1451 94 5.0 mev 11 1146 1451 95 6.0 mev 9,7(from p+t elastic scatt) 1146 1451 96 8.0 mev 11,7(from p+t elastic scatt) 1146 1451 97 14.5 mev 16,17(from p+t elastic scatt)1146 1451 98 17.5 mev 11 1146 1451 99 20.0 mev 2(from p+t elastic scatt) 1146 1451 100 1146 1451 101 references 1146 1451 102 1146 1451 103 1. r.batchelor,r.aves,and t.h.r.skyrme,rev.sci.instr.26,1037 1146 1451 104 (1955). 1146 1451 105 2. r.a.vanetsian and e.d.fenchenko,soviet journal of atomic 1146 1451 106 energy 2,141(1957). 1146 1451 107 3. j.n.bradbury and l.stewart,bull.am.phys.soc.3,417(1958) 1146 1451 108 4. g.f.bogdanov,n.a.vlasov,c.p.kalinin,b.v.rybakov,l.n. 1146 1451 109 samoilov,and v.a.sidorov,jetp(ussr)36,633(1959). 1146 1451 110 5. j.h.gibbons and r.l.macklin,phys.rev.114,571(1959). 1146 1451 111 6. los alamos physics and cryogenics groups,nucl.phys.12, 1146 1451 112 291(1959). 1146 1451 113 7. j.e.brolley,jr.,t.m.putnam,l.rosen,and l.stewart,phys. 1146 1451 114 rev.159,777(1967). 1146 1451 115 8. j.e.perry,private communication to stewart(1960) 1146 1451 116 9. j.d.seagrave,l.cranberg,and j.e.simmons,phys.rev.119, 1146 1451 117 1981(1960) 1146 1451 118 10. m.d.goldberg,j.d.anderson,j.p.stoering,and c.wong,phys. 1146 1451 119 rev.122,1510(1961). 1146 1451 120 11. a.r.sayers,k.w.jones,and c.s.wu,phys.rev.122,1853(1961). 1146 1451 121 12. w.e.wilson,r.l.walter,and d.b.fossan,nucl.phys.27,421 1146 1451 122 (1961). 1146 1451 123 13. j.als-nielsen and o.dietrich,phys.rev.133,b925(1964). 1146 1451 124 14. r.l.macklin and j.h.gibbons,proceedings of the internatl. 1146 1451 125 conf.on the study of nucl.struct.with neuts.,antwerp(1965)1146 1451 126 15. j.h.gibbons,private communication to stewart(1966). 1146 1451 127 16. b.antolkovic,g.paic,p.tomas,and r.rendic,phys.rev.159, 1146 1451 128 777(1967). 1146 1451 129 17. l.rosen and w.leland,private communication(1967) 1146 1451 130 1146 1451 131 1 451 141 11146 1451 132 2 151 4 01146 1451 133 3 1 30 01146 1451 134 3 2 30 01146 1451 135 3 103 30 01146 1451 136 3 104 13 01146 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300 5.33216- 3-2.60015- 2 9.28915- 2-2.38457- 1 4.02574- 1-3.47398- 11146 4 2 301 -8.25184- 3-5.55962- 6 0.00000+ 0-2.44927- 5 2.72117- 4-2.01997- 31146 4 2 302 1.07487- 2-4.34256- 2 1.31946- 1-2.89392- 1 4.11712- 1-2.73002- 11146 4 2 303 -5.68753- 2 1146 4 2 304 0.00000+ 0 0.00000+ 0 0 0 1 121146 4 2 305 12 2 1146 4 2 306 0.00000+ 0 1.00000- 5 0 0 1 21146 4 2 307 2 2 1146 4 2 308 -1.00000+ 0 5.00000- 1 1.00000+ 0 5.00000- 1 1146 4 2 309 0.00000+ 0 5.00000+ 5 0 0 1 21146 4 2 310 2 2 1146 4 2 311 -1.00000+ 0 5.00000- 1 1.00000+ 0 5.00000- 1 1146 4 2 312 0.00000+ 0 1.00000+ 6 0 0 1 211146 4 2 313 21 2 1146 4 2 314 -1.00000+ 0 9.34700- 1-9.00000- 1 8.64300- 1-8.00000- 1 7.93900- 11146 4 2 315 -7.00000- 1 7.23400- 1-6.00000- 1 6.59400- 1-5.00000- 1 5.98600- 11146 4 2 316 -4.00000- 1 5.44200- 1-3.00000- 1 4.99400- 1-2.00000- 1 4.54600- 11146 4 2 317 -1.00000- 1 4.22500- 1 0.00000+ 0 3.90500- 1 1.00000- 1 3.71300- 11146 4 2 318 2.00000- 1 3.58500- 1 3.00000- 1 3.52100- 1 4.00000- 1 3.52100- 11146 4 2 319 5.00000- 1 3.58500- 1 6.00000- 1 3.68100- 1 7.00000- 1 3.80900- 11146 4 2 320 8.00000- 1 4.00100- 1 9.00000- 1 4.19300- 1 1.00000+ 0 4.41700- 11146 4 2 321 0.00000+ 0 2.00000+ 6 0 0 1 211146 4 2 322 21 2 1146 4 2 323 -1.00000+ 0 8.83500- 1-9.00000- 1 7.63100- 1-8.00000- 1 6.52700- 11146 4 2 324 -7.00000- 1 5.57300- 1-6.00000- 1 4.66900- 1-5.00000- 1 3.94100- 11146 4 2 325 -4.00000- 1 3.38900- 1-3.00000- 1 3.01200- 1-2.00000- 1 2.76100- 11146 4 2 326 -1.00000- 1 2.71100- 1 0.00000+ 0 2.81100- 1 1.00000- 1 2.98700- 11146 4 2 327 2.00000- 1 3.26300- 1 3.00000- 1 3.58900- 1 4.00000- 1 4.06700- 11146 4 2 328 5.00000- 1 4.73500- 1 6.00000- 1 5.47200- 1 7.00000- 1 6.47600- 11146 4 2 329 8.00000- 1 7.65600- 1 9.00000- 1 9.08700- 1 1.00000+ 0 1.04460+ 01146 4 2 330 0.00000+ 0 2.60000+ 6 0 0 1 211146 4 2 331 21 2 1146 4 2 332 -1.00000+ 0 7.61900- 1-9.00000- 1 6.39300- 1-8.00000- 1 5.43400- 11146 4 2 333 -7.00000- 1 4.66200- 1-6.00000- 1 3.99600- 1-5.00000- 1 3.41000- 11146 4 2 334 -4.00000- 1 2.95700- 1-3.00000- 1 2.58400- 1-2.00000- 1 2.31800- 11146 4 2 335 -1.00000- 1 2.23800- 1 0.00000+ 0 2.53100- 1 1.00000- 1 2.95700- 11146 4 2 336 2.00000- 1 3.46300- 1 3.00000- 1 4.10200- 1 4.00000- 1 4.84800- 11146 4 2 337 5.00000- 1 5.75400- 1 6.00000- 1 6.66000- 1 7.00000- 1 7.67200- 11146 4 2 338 8.00000- 1 8.73700- 1 9.00000- 1 9.91000- 1 1.00000+ 0 1.11300+ 01146 4 2 339 0.00000+ 0 3.50000+ 6 0 0 1 211146 4 2 340 21 2 1146 4 2 341 -1.00000+ 0 6.96500- 1-9.00000- 1 5.72800- 1-8.00000- 1 4.62500- 11146 4 2 342 -7.00000- 1 3.71100- 1-6.00000- 1 2.90400- 1-5.00000- 1 2.28500- 11146 4 2 343 -4.00000- 1 1.82800- 1-3.00000- 1 1.61300- 1-2.00000- 1 1.61300- 11146 4 2 344 -1.00000- 1 1.82800- 1 0.00000+ 0 2.20500- 1 1.00000- 1 2.74300- 11146 4 2 345 2.00000- 1 3.41500- 1 3.00000- 1 4.24800- 1 4.00000- 1 5.16300- 11146 4 2 346 5.00000- 1 6.18500- 1 6.00000- 1 7.39500- 1 7.00000- 1 8.84700- 11146 4 2 347 8.00000- 1 1.06210+ 0 9.00000- 1 1.24860+ 0 1.00000+ 0 1.41510+ 01146 4 2 348 0.00000+ 0 5.00000+ 6 0 0 1 211146 4 2 349 21 2 1146 4 2 350 -1.00000+ 0 5.89400- 1-9.00000- 1 4.42100- 1-8.00000- 1 3.30700- 11146 4 2 351 -7.00000- 1 2.55400- 1-6.00000- 1 1.93200- 1-5.00000- 1 1.60500- 11146 4 2 352 -4.00000- 1 1.34200- 1-3.00000- 1 1.31000- 1-2.00000- 1 1.31000- 11146 4 2 353 -1.00000- 1 1.40800- 1 0.00000+ 0 1.70200- 1 1.00000- 1 2.19400- 11146 4 2 354 2.00000- 1 3.04500- 1 3.00000- 1 4.19100- 1 4.00000- 1 5.40300- 11146 4 2 355 5.00000- 1 7.07300- 1 6.00000- 1 8.84100- 1 7.00000- 1 1.06400+ 01146 4 2 356 8.00000- 1 1.24400+ 0 9.00000- 1 1.43100+ 0 1.00000+ 0 1.60500+ 01146 4 2 357 0.00000+ 0 6.00000+ 6 0 0 1 211146 4 2 358 21 2 1146 4 2 359 -1.00000+ 0 5.65100- 1-9.00000- 1 4.11000- 1-8.00000- 1 3.00900- 11146 4 2 360 -7.00000- 1 2.16500- 1-6.00000- 1 1.54100- 1-5.00000- 1 1.17400- 11146 4 2 361 -4.00000- 1 8.81000- 2-3.00000- 1 7.34000- 2-2.00000- 1 8.07000- 21146 4 2 362 -1.00000- 1 1.17400- 1 0.00000+ 0 1.68800- 1 1.00000- 1 2.49500- 11146 4 2 363 2.00000- 1 3.59600- 1 3.00000- 1 4.91700- 1 4.00000- 1 6.31200- 11146 4 2 364 5.00000- 1 7.78000- 1 6.00000- 1 9.24800- 1 7.00000- 1 1.08600+ 01146 4 2 365 8.00000- 1 1.24800+ 0 9.00000- 1 1.40900+ 0 1.00000+ 0 1.62210+ 01146 4 2 366 0.00000+ 0 8.00000+ 6 0 0 1 211146 4 2 367 21 2 1146 4 2 368 -1.00000+ 0 5.15200- 1-9.00000- 1 3.78700- 1-8.00000- 1 2.64200- 11146 4 2 369 -7.00000- 1 1.71700- 1-6.00000- 1 1.10100- 1-5.00000- 1 6.61000- 21146 4 2 370 -4.00000- 1 5.28000- 2-3.00000- 1 6.17000- 2-2.00000- 1 7.93000- 21146 4 2 371 -1.00000- 1 1.14500- 1 0.00000+ 0 1.62900- 1 1.00000- 1 2.29000- 11146 4 2 372 2.00000- 1 3.12600- 1 3.00000- 1 4.13900- 1 4.00000- 1 5.50400- 11146 4 2 373 5.00000- 1 7.22200- 1 6.00000- 1 9.29100- 1 7.00000- 1 1.16700+ 01146 4 2 374 8.00000- 1 1.41300+ 0 9.00000- 1 1.64700+ 0 1.00000+ 0 1.79210+ 01146 4 2 375 0.00000+ 0 1.50000+ 7 0 0 1 211146 4 2 376 21 2 1146 4 2 377 -1.00000+ 0 2.94800- 1-9.00000- 1 2.13300- 1-8.00000- 1 1.40500- 11146 4 2 378 -7.00000- 1 1.03300- 1-6.00000- 1 8.15000- 2-5.00000- 1 6.50000- 21146 4 2 379 -4.00000- 1 5.79000- 2-3.00000- 1 6.67000- 2-2.00000- 1 8.82000- 21146 4 2 380 -1.00000- 1 1.24600- 1 0.00000+ 0 1.69400- 1 1.00000- 1 2.19400- 11146 4 2 381 2.00000- 1 2.80800- 1 3.00000- 1 3.65500- 1 4.00000- 1 4.76000- 11146 4 2 382 5.00000- 1 6.33100- 1 6.00000- 1 9.23400- 1 7.00000- 1 1.25290+ 01146 4 2 383 8.00000- 1 1.57290+ 0 9.00000- 1 1.90790+ 0 1.00000+ 0 2.22090+ 01146 4 2 384 0.00000+ 0 1.75000+ 7 0 0 1 211146 4 2 385 21 2 1146 4 2 386 -1.00000+ 0 2.35600- 1-9.00000- 1 1.36500- 1-8.00000- 1 9.63000- 21146 4 2 387 -7.00000- 1 7.85000- 2-6.00000- 1 7.10000- 2-5.00000- 1 7.01000- 21146 4 2 388 -4.00000- 1 7.20000- 2-3.00000- 1 7.76000- 2-2.00000- 1 8.79000- 21146 4 2 389 -1.00000- 1 1.03800- 1 0.00000+ 0 1.29000- 1 1.00000- 1 1.66400- 11146 4 2 390 2.00000- 1 2.18700- 1 3.00000- 1 2.97300- 1 4.00000- 1 4.14100- 11146 4 2 391 5.00000- 1 5.81400- 1 6.00000- 1 8.13200- 1 7.00000- 1 1.13110+ 01146 4 2 392 8.00000- 1 1.57970+ 0 9.00000- 1 2.21540+ 0 1.00000+ 0 3.08470+ 01146 4 2 393 0.00000+ 0 2.00000+ 7 0 0 1 211146 4 2 394 21 2 1146 4 2 395 -1.00000+ 0 3.89900- 1-9.00000- 1 2.34800- 1-8.00000- 1 1.46100- 11146 4 2 396 -7.00000- 1 9.41000- 2-6.00000- 1 6.36000- 2-5.00000- 1 4.48000- 21146 4 2 397 -4.00000- 1 5.02000- 2-3.00000- 1 6.99000- 2-2.00000- 1 9.50000- 21146 4 2 398 -1.00000- 1 1.28200- 1 0.00000+ 0 1.72100- 1 1.00000- 1 2.29400- 11146 4 2 399 2.00000- 1 3.04700- 1 3.00000- 1 4.06900- 1 4.00000- 1 5.36000- 11146 4 2 400 5.00000- 1 6.99100- 1 6.00000- 1 9.14200- 1 7.00000- 1 1.15620+ 01146 4 2 401 8.00000- 1 1.46990+ 0 9.00000- 1 1.84640+ 0 1.00000+ 0 2.28560+ 01146 4 2 402 0.00000+ 0 0.00000+ 0 0 0 0 01146 4 0 403 0.00000+ 0 0.00000+ 0 0 0 0 01146 0 0 404 0.00000+ 0 0.00000+ 0 0 0 0 0 0 0 0 405 1.00100+ 3 9.99170- 1 0 0 0 11301 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 01301 1451 2 0.00000+ 0 0.00000+ 0 0 0 96 141301 1451 3 1-h - 10lasl eval-aug70 l.stewart, r.j.labauve, p.g.young1301 1451 4 la-4574 (1971) dist-may79 rev1-jan77 790426 1301 1451 5 1301 1451 6 ******************************************************************1301 1451 7 1301 1451 8 1301 1451 9 changes from version iv to version v 1301 1451 10 1301 1451 11 1. interpolation rules on mt=1 and mt=2 1301 1451 12 2. file 33 added. 1301 1451 13 1301 1451 14 changes from version iii to version iv 1301 1451 15 1301 1451 16 1. totals reconstructed to higher precision 1301 1451 17 2. the lp flag has been implemented in file 12, mt=102 1301 1451 18 1301 1451 19 ******************************************************************1301 1451 20 1301 1451 21 cross section standard - hydrogen scattering cross section 1301 1451 22 1301 1451 23 1 kev - 20 mev 1301 1451 24 1301 1451 25 recommended by csewg normalization and standards subcommittee 1301 1451 26 1301 1451 27 for a complete description of version iv see la-6518-ms 1301 1451 28 by g.m.hale, l.stewart, and p.g.young 1301 1451 29 1301 1451 30 ******************************************************************1301 1451 31 1301 1451 32 1301 1451 33 mf=1 1301 1451 34 1301 1451 35 mt=451, atomic mass=1.007825 1301 1451 36 1301 1451 37 mf=2 1301 1451 38 1301 1451 39 mt=151, scattering length=1.27565e-12 cm. 1301 1451 40 1301 1451 41 mf=3 1301 1451 42 1301 1451 43 mt= 1, total cross sections --- the total cross sections are 1301 1451 44 obtained by adding the elastic scattering and 1301 1451 45 radiative capture cross sections at all energies. 1301 1451 46 1.0e-05 ev to 20 mev. 1301 1451 47 1301 1451 48 mt= 2, elastic scattering --- from an extensive theoretical 1301 1451 49 treatment of fast neutron measurements 1301 1451 50 by j. c. hopkins(lasl) and g. breit(state 1301 1451 51 university of new york). see n.d. a9, 145(1971). 1301 1451 52 1.0e-05 ev to 20 mev. 1301 1451 53 1301 1451 54 mt=102, radiative capture --- these cross sections are taken 1301 1451 55 from the publication of a. horley where a value 1301 1451 56 of 332 mb was adopted for the thermal value. see 1301 1451 57 n.d. a2, 243(1966) also p.c. 1301 1451 58 1.0e-05 ev to 20 mev. 1301 1451 59 1301 1451 60 mt=251, average value of cosine of scattering angle 1301 1451 61 in lab system (provided by bnl). 1301 1451 62 1.0e-05 ev t0 20 mev. 1301 1451 63 1301 1451 64 mt=252, average logarithmic energy change per collison, 1301 1451 65 , from 1.0e-05 ev to 20 mev. (provided by bnl). 1301 1451 66 1301 1451 67 mt=253, gamma, , from 1.0e-05 ev to 20 mev. 1301 1451 68 (provided by bnl). 1301 1451 69 1301 1451 70 mf=4 1301 1451 71 1301 1451 72 mt= 2, neutron elastic scattering angular distributions in 1301 1451 73 the center of mass system--given as normalized 1301 1451 74 pointwise probabilities. 1301 1451 75 1301 1451 76 1301 1451 77 mf=7 1301 1451 78 1301 1451 79 mt= 4, .00001 to 5 ev free gas sigma=20.449 barns. 1301 1451 80 1301 1451 81 mf=12 1301 1451 82 1301 1451 83 mt=102, gamma ray multiplicities --- multiplicity, (referred 1301 1451 84 to mt=102, mf=3), is unity at all neutron energies. 1301 1451 85 lp=2 now implemented, therefore all gamma energies 1301 1451 86 must be calculated. 1301 1451 87 1301 1451 88 mf=14 1301 1451 89 1301 1451 90 mt=102, gamma ray angular distribution --- assumed isotropic 1301 1451 91 at all neutron energies. 1301 1451 92 1301 1451 93 mf=33 1301 1451 94 1301 1451 95 mt=2, covariance matrices added for the elastic scattering by 1301 1451 96 d.g.foster,jr. (jan 77). 1301 1451 97 1301 1451 98 1301 1451 99 1 451 113 01301 1451 100 2 151 4 01301 1451 101 3 1 48 11301 1451 102 3 2 48 11301 1451 103 3 102 48 01301 1451 104 3 251 8 11301 1451 105 3 252 8 01301 1451 106 3 253 8 01301 1451 107 4 2 162 11301 1451 108 12 102 4 01301 1451 109 14 102 1 01301 1451 110 33 1 5 11301 1451 111 33 2 25 11301 1451 112 33 102 9 11301 1451 113 0.00000+ 0 0.00000+ 0 0 0 0 01301 1 0 114 0.00000+ 0 0.00000+ 0 0 0 0 01301 0 0 115 1.00100+ 3 9.99170- 1 0 0 1 01301 2151 116 1.00100+ 3 1.00000+ 0 0 0 1 01301 2151 117 1.00000- 5 1.00000+ 5 0 0 0 01301 2151 118 5.00000- 1 1.27565+ 0 0 0 0 01301 2151 119 0.00000+ 0 0.00000+ 0 0 0 0 01301 2 0 120 0.00000+ 0 0.00000+ 0 0 0 0 01301 0 0 121 1.00100+ 3 9.99170- 1 0 0 0 01301 3 1 122 0.00000+ 0 0.00000+ 0 0 0 2 1341301 3 1 123 15 5 134 2 1301 3 1 124 1.00000- 5 3.71480+ 1 2.00000- 5 3.22570+ 1 5.00000- 5 2.79170+ 11301 3 1 125 1.00000- 4 2.57300+ 1 2.00000- 4 2.41830+ 1 5.00000- 4 2.28110+ 11301 3 1 126 1.00000- 3 2.21190+ 1 2.00000- 3 2.16300+ 1 5.00000- 3 2.11960+ 11301 3 1 127 1.00000- 2 2.09770+ 1 2.53000- 2 2.07810+ 1 1.00000+ 2 2.04540+ 11301 3 1 128 1.00000+ 3 2.03310+ 1 2.00000+ 3 2.01990+ 1 3.00000+ 3 2.00690+ 11301 3 1 129 4.00000+ 3 1.99420+ 1 5.00000+ 3 1.98160+ 1 6.00000+ 3 1.96920+ 11301 3 1 130 8.00000+ 3 1.94490+ 1 1.00000+ 4 1.92130+ 1 1.50000+ 4 1.86510+ 11301 3 1 131 2.00000+ 4 1.81260+ 1 2.50000+ 4 1.76340+ 1 3.00000+ 4 1.71720+ 11301 3 1 132 3.50000+ 4 1.67370+ 1 4.00000+ 4 1.63270+ 1 4.50000+ 4 1.59410+ 11301 3 1 133 5.00000+ 4 1.55750+ 1 5.50000+ 4 1.52280+ 1 6.00000+ 4 1.49000+ 11301 3 1 134 6.50000+ 4 1.45870+ 1 7.00000+ 4 1.42910+ 1 7.50000+ 4 1.40080+ 11301 3 1 135 8.00000+ 4 1.37380+ 1 8.50000+ 4 1.34810+ 1 9.00000+ 4 1.32350+ 11301 3 1 136 9.50000+ 4 1.29990+ 1 1.00000+ 5 1.27740+ 1 1.10000+ 5 1.23510+ 11301 3 1 137 1.20000+ 5 1.19640+ 1 1.30000+ 5 1.16070+ 1 1.40000+ 5 1.12750+ 11301 3 1 138 1.50000+ 5 1.09650+ 1 1.60000+ 5 1.06730+ 1 1.70000+ 5 1.03980+ 11301 3 1 139 1.80000+ 5 1.01400+ 1 1.90000+ 5 9.89810+ 0 2.00000+ 5 9.67110+ 01301 3 1 140 2.20000+ 5 9.25810+ 0 2.40000+ 5 8.89210+ 0 2.60000+ 5 8.56200+ 01301 3 1 141 2.80000+ 5 8.26200+ 0 3.00000+ 5 7.98700+ 0 3.20000+ 5 7.73400+ 01301 3 1 142 3.40000+ 5 7.50100+ 0 3.60000+ 5 7.28400+ 0 3.80000+ 5 7.08300+ 01301 3 1 143 4.00000+ 5 6.89700+ 0 4.20000+ 5 6.72500+ 0 4.40000+ 5 6.56500+ 01301 3 1 144 4.60000+ 5 6.41500+ 0 4.80000+ 5 6.27500+ 0 5.00000+ 5 6.14300+ 01301 3 1 145 5.50000+ 5 5.84500+ 0 6.00000+ 5 5.58400+ 0 6.50000+ 5 5.35400+ 01301 3 1 146 7.00000+ 5 5.14800+ 0 7.50000+ 5 4.96400+ 0 8.00000+ 5 4.79700+ 01301 3 1 147 8.50000+ 5 4.64500+ 0 9.00000+ 5 4.50600+ 0 9.50000+ 5 4.37800+ 01301 3 1 148 1.00000+ 6 4.26100+ 0 1.10000+ 6 4.05100+ 0 1.20000+ 6 3.86800+ 01301 3 1 149 1.30000+ 6 3.70600+ 0 1.40000+ 6 3.56100+ 0 1.50000+ 6 3.42900+ 01301 3 1 150 1.60000+ 6 3.30900+ 0 1.70000+ 6 3.19800+ 0 1.80000+ 6 3.09700+ 01301 3 1 151 1.90000+ 6 3.00300+ 0 2.00000+ 6 2.91500+ 0 2.20000+ 6 2.75900+ 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5-2.12143- 4-2.03807- 4-3.14538- 5-3.81690- 51301 4 2 370 -1.92337- 4-1.62967- 4 5.15805- 6-1.75527- 5-1.85345- 4-1.60907- 41301 4 2 371 2.27773- 5 2.42385- 5-1.74251- 4 0.00000 0 0.00000 0 0.00000 01301 4 2 372 0.00000+ 0 0.00000+ 0 0 0 1 141301 4 2 373 14 2 1301 4 2 374 0.00000+ 0 1.00000- 5 0 0 1 111301 4 2 375 11 2 1301 4 2 376 -1.00000+ 0 5.00000- 1-8.00000- 1 5.00000- 1-6.00000- 1 5.00000- 11301 4 2 377 -4.00000- 1 5.00000- 1-2.00000- 1 5.00000- 1 0.00000+ 0 5.00000- 11301 4 2 378 2.00000- 1 5.00000- 1 4.00000- 1 5.00000- 1 6.00000- 1 5.00000- 11301 4 2 379 8.00000- 1 5.00000- 1 1.00000+ 0 5.00000- 1 1301 4 2 380 0.00000+ 0 1.00000+ 5 0 0 1 111301 4 2 381 11 2 1301 4 2 382 -1.00000+ 0 5.00000- 1-8.00000- 1 5.00000- 1-6.00000- 1 5.00000- 11301 4 2 383 -4.00000- 1 5.00000- 1-2.00000- 1 5.00000- 1 0.00000+ 0 5.00000- 11301 4 2 384 2.00000- 1 5.00000- 1 4.00000- 1 5.00000- 1 6.00000- 1 5.00000- 11301 4 2 385 8.00000- 1 5.00000- 1 1.00000+ 0 5.00000- 1 1301 4 2 386 0.00000+ 0 5.00000+ 5 0 0 1 111301 4 2 387 11 2 1301 4 2 388 -1.00000+ 0 5.01170- 1-8.00000- 1 5.00970- 1-6.00000- 1 5.00660- 11301 4 2 389 -4.00000- 1 5.00450- 1-2.00000- 1 5.00250- 1 0.00000+ 0 5.00050- 11301 4 2 390 2.00000- 1 4.99740- 1 4.00000- 1 4.99530- 1 6.00000- 1 4.99330- 11301 4 2 391 8.00000- 1 4.99020- 1 1.00000+ 0 4.98820- 1 1301 4 2 392 0.00000+ 0 1.00000+ 6 0 0 1 111301 4 2 393 11 2 1301 4 2 394 -1.00000+ 0 5.02180- 1-8.00000- 1 5.01760- 1-6.00000- 1 5.01310- 11301 4 2 395 -4.00000- 1 5.00890- 1-2.00000- 1 5.00440- 1 0.00000+ 0 5.00000- 11301 4 2 396 2.00000- 1 4.99570- 1 4.00000- 1 4.99130- 1 6.00000- 1 4.98690- 11301 4 2 397 8.00000- 1 4.98230- 1 1.00000+ 0 4.97790- 1 1301 4 2 398 0.00000+ 0 2.00000+ 6 0 0 1 111301 4 2 399 11 2 1301 4 2 400 -1.00000+ 0 5.03870- 1-8.00000- 1 5.03110- 1-6.00000- 1 5.02340- 11301 4 2 401 -4.00000- 1 5.01580- 1-2.00000- 1 5.00810- 1 0.00000+ 0 5.00030- 11301 4 2 402 2.00000- 1 4.99250- 1 4.00000- 1 4.98460- 1 6.00000- 1 4.97640- 11301 4 2 403 8.00000- 1 4.96820- 1 1.00000+ 0 4.95980- 1 1301 4 2 404 0.00000+ 0 4.00000+ 6 0 0 1 111301 4 2 405 11 2 1301 4 2 406 -1.00000+ 0 5.06770- 1-8.00000- 1 5.05420- 1-6.00000- 1 5.04070- 11301 4 2 407 -4.00000- 1 5.02750- 1-2.00000- 1 5.01430- 1 0.00000+ 0 5.00110- 11301 4 2 408 2.00000- 1 4.98730- 1 4.00000- 1 4.97340- 1 6.00000- 1 4.95890- 11301 4 2 409 8.00000- 1 4.94410- 1 1.00000+ 0 4.92830- 1 1301 4 2 410 0.00000+ 0 6.00000+ 6 0 0 1 111301 4 2 411 11 2 1301 4 2 412 -1.00000+ 0 5.09990- 1-8.00000- 1 5.07700- 1-6.00000- 1 5.05600- 11301 4 2 413 -4.00000- 1 5.03620- 1-2.00000- 1 5.01770- 1 0.00000+ 0 4.99930- 11301 4 2 414 2.00000- 1 4.98080- 1 4.00000- 1 4.96280- 1 6.00000- 1 4.94390- 11301 4 2 415 8.00000- 1 4.92460- 1 1.00000+ 0 4.90400- 1 1301 4 2 416 0.00000+ 0 8.00000+ 6 0 0 1 111301 4 2 417 11 2 1301 4 2 418 -1.00000+ 0 5.12880- 1-8.00000- 1 5.09520- 1-6.00000- 1 5.06760- 11301 4 2 419 -4.00000- 1 5.04340- 1-2.00000- 1 5.02070- 1 0.00000+ 0 4.99870- 11301 4 2 420 2.00000- 1 4.97660- 1 4.00000- 1 4.95460- 1 6.00000- 1 4.93140- 11301 4 2 421 8.00000- 1 4.90770- 1 1.00000+ 0 4.88180- 1 1301 4 2 422 0.00000+ 0 1.00000+ 7 0 0 1 111301 4 2 423 11 2 1301 4 2 424 -1.00000+ 0 5.17270- 1-8.00000- 1 5.12010- 1-6.00000- 1 5.07940- 11301 4 2 425 -4.00000- 1 5.04610- 1-2.00000- 1 5.01680- 1 0.00000+ 0 4.99080- 11301 4 2 426 2.00000- 1 4.96690- 1 4.00000- 1 4.94350- 1 6.00000- 1 4.92020- 11301 4 2 427 8.00000- 1 4.89690- 1 1.00000+ 0 4.87160- 1 1301 4 2 428 0.00000+ 0 1.20000+ 7 0 0 1 121301 4 2 429 12 2 1301 4 2 430 -1.00000+ 0 5.22667- 1-9.00000- 1 5.18198- 1-8.00000- 1 5.14588- 11301 4 2 431 -6.00000- 1 5.08929- 1-4.00000- 1 5.04699- 1-2.00000- 1 5.01239- 11301 4 2 432 0.00000+ 0 4.98180- 1 2.00000- 1 4.95510- 1 4.00000- 1 4.93080- 11301 4 2 433 6.00000- 1 4.90800- 1 8.00000- 1 4.88611- 1 1.00000+ 0 4.86491- 11301 4 2 434 0.00000+ 0 1.40000+ 7 0 0 1 121301 4 2 435 12 2 1301 4 2 436 -1.00000+ 0 5.28156- 1-9.00000- 1 5.21807- 1-8.00000- 1 5.16907- 11301 4 2 437 -6.00000- 1 5.09748- 1-4.00000- 1 5.04489- 1-2.00000- 1 5.00410- 11301 4 2 438 0.00000+ 0 4.96960- 1 2.00000- 1 4.94241- 1 4.00000- 1 4.91881- 11301 4 2 439 6.00000- 1 4.89981- 1 8.00000- 1 4.88261- 1 1.00000+ 0 4.86812- 11301 4 2 440 0.00000+ 0 1.60000+ 7 0 0 1 121301 4 2 441 12 2 1301 4 2 442 -1.00000+ 0 5.34226- 1-9.00000- 1 5.25648- 1-8.00000- 1 5.19139- 11301 4 2 443 -6.00000- 1 5.10141- 1-4.00000- 1 5.03942- 1-2.00000- 1 4.99293- 11301 4 2 444 0.00000+ 0 4.95574- 1 2.00000- 1 4.92784- 1 4.00000- 1 4.90715- 11301 4 2 445 6.00000- 1 4.89265- 1 8.00000- 1 4.88435- 1 1.00000+ 0 4.88235- 11301 4 2 446 0.00000+ 0 1.80000+ 7 0 0 1 121301 4 2 447 12 2 1301 4 2 448 -1.00000+ 0 5.40750- 1-9.00000- 1 5.29454- 1-8.00000- 1 5.21176- 11301 4 2 449 -6.00000- 1 5.10220- 1-4.00000- 1 5.03112- 1-2.00000- 1 4.97864- 11301 4 2 450 0.00000+ 0 4.93905- 1 2.00000- 1 4.91106- 1 4.00000- 1 4.89476- 11301 4 2 451 6.00000- 1 4.88896- 1 8.00000- 1 4.89246- 1 1.00000+ 0 4.90756- 11301 4 2 452 0.00000+ 0 2.00000+ 7 0 0 1 121301 4 2 453 12 2 1301 4 2 454 -1.00000+ 0 5.47851- 1-9.00000- 1 5.33267- 1-8.00000- 1 5.23111- 11301 4 2 455 -6.00000- 1 5.10086- 1-4.00000- 1 5.02009- 1-2.00000- 1 4.96152- 11301 4 2 456 0.00000+ 0 4.91983- 1 2.00000- 1 4.89384- 1 4.00000- 1 4.88205- 11301 4 2 457 6.00000- 1 4.88465- 1 8.00000- 1 4.90554- 1 1.00000+ 0 4.94462- 11301 4 2 458 0.00000+ 0 0.00000+ 0 0 0 0 01301 4 0 459 0.00000+ 0 0.00000+ 0 0 0 0 01301 0 0 460 1.00100+ 3 9.99170- 1 1 0 1 0130112102 461 2.22460+ 6 0.00000+ 0 2 2 1 2130112102 462 2 2 130112102 463 1.00000- 5 1.00000+ 0 2.00000+ 7 1.00000+ 0 130112102 464 0.00000+ 0 0.00000+ 0 0 0 0 0130112 0 465 0.00000+ 0 0.00000+ 0 0 0 0 01301 0 0 466 1.00100+ 3 9.99170- 1 1 0 1 0130114102 467 0.00000+ 0 0.00000+ 0 0 0 0 0130114 0 468 0.00000+ 0 0.00000+ 0 0 0 0 01301 0 0 469 1.00100+ 3 9.99170- 1 0 0 0 1130133 1 470 0.00000+ 0 0.00000+ 0 0 1 1 0130133 1 471 0.00000+ 0 0.00000+ 0 0 0 0 0130133 1 472 1.00000- 5 2.00000+ 7 0 0 4 2130133 1 473 1.00000+ 0 2.00000+ 0 1.00000+ 0 1.02000+ 2 130133 1 474 0.00000+ 0 0.00000+ 0 0 0 0 0130133 0 475 1.00100+ 3 9.99170- 1 0 0 0 1130133 2 476 0.00000+ 0 0.00000+ 0 0 2 0 5130133 2 477 0.00000+ 0 0.00000+ 0 6 3 18 9130133 2 478 1.00000- 5 1.00000- 4 1.00000+ 3 0.00000+ 0 2.00000+ 7 0.00000+ 0130133 2 479 1.00000- 5 1.00000+ 0 1.00000+ 3 1.70000- 1 1.00000+ 5-5.00000- 2130133 2 480 1.00000+ 6-2.00000- 2 1.40000+ 7 1.00000- 2 2.00000+ 7 0.00000+ 0130133 2 481 0.00000+ 0 0.00000+ 0 6 3 20 10130133 2 482 1.00000- 5 0.00000+ 0 1.00000+ 3 1.00000- 4 1.00000+ 5 0.00000+ 0130133 2 483 2.00000+ 7 0.00000+ 0 1.00000- 5 1.70000- 1 1.00000+ 3 2.50000- 1130133 2 484 1.00000+ 5 1.20000- 1 1.00000+ 6-5.00000- 2 1.40000+ 7-2.00000- 2130133 2 485 2.00000+ 7 0.00000+ 0 130133 2 486 0.00000+ 0 0.00000+ 0 6 3 20 10130133 2 487 1.00000- 5 0.00000+ 0 1.00000+ 5 1.00000- 4 1.00000+ 6 0.00000+ 0130133 2 488 2.00000+ 7 0.00000+ 0 1.00000- 5-5.00000- 2 1.00000+ 3 1.20000- 1130133 2 489 1.00000+ 5 5.00000- 1 1.00000+ 6 2.00000- 1 1.40000+ 7-8.00000- 2130133 2 490 2.00000+ 7 0.00000+ 0 130133 2 491 0.00000+ 0 0.00000+ 0 6 3 20 10130133 2 492 1.00000- 5 0.00000+ 0 1.00000+ 6 1.00000- 4 1.40000+ 7 0.00000+ 0130133 2 493 2.00000+ 7 0.00000+ 0 1.00000- 5-2.00000- 2 1.00000+ 3-5.00000- 2130133 2 494 1.00000+ 5 2.00000- 1 1.00000+ 6 7.50000- 1 1.40000+ 7 2.90000- 1130133 2 495 2.00000+ 7 0.00000+ 0 130133 2 496 0.00000+ 0 0.00000+ 0 6 3 18 9130133 2 497 1.00000- 5 0.00000+ 0 1.40000+ 7 1.00000- 4 2.00000+ 7 0.00000+ 0130133 2 498 1.00000- 5 1.00000- 2 1.00000+ 3-2.00000- 2 1.00000+ 5-8.00000- 2130133 2 499 1.00000+ 6 2.90000- 1 1.40000+ 7 1.00000+ 0 2.00000+ 7 0.00000+ 0130133 2 500 0.00000+ 0 0.00000+ 0 0 0 0 0130133 0 501 1.00100+ 3 9.99170- 1 0 0 0 1130133102 502 0.00000+ 0 0.00000+ 0 0 102 0 2130133102 503 0.00000+ 0 0.00000+ 0 0 2 8 4130133102 504 1.00000- 5 6.00000- 3 1.00000+ 4 1.00000- 2 2.00000+ 5 2.00000- 2130133102 505 2.00000+ 7 0.00000+ 0 130133102 506 0.00000+ 0 0.00000+ 0 0 2 14 7130133102 507 1.00000- 5 0.00000+ 0 2.00000+ 5 1.00000- 2 1.00000+ 6 2.00000- 2130133102 508 5.00000+ 6 4.00000- 2 1.00000+ 7 6.00000- 2 1.60000+ 7 9.00000- 2130133102 509 2.00000+ 7 0.00000+ 0 130133102 510 0.00000+ 0 0.00000+ 0 0 0 0 0130133 0 511 0.00000+ 0 0.00000+ 0 0 0 0 01301 0 0 512 0.00000+ 0 0.00000+ 0 0 0 0 0 0 0 0 513 3.00600+ 3 5.96340+ 0 0 0 0 11303 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 01303 1451 2 0.00000+ 0 0.00000+ 0 0 0 222 891303 1451 3 3-li-0060lasl eval-sep77 g.hale, l.stewart, p.g.young 1303 1451 4 dist-may79 rev1-sep77 790426 1303 1451 5 1303 1451 6 ******************************************************************1303 1451 7 1303 1451 8 changes from version iv 1303 1451 9 1. all cross sections revised except for the (n,gamma). 1303 1451 10 2. pseudo-level representation used for the (n,nprime)d 1303 1451 11 continuum. 1303 1451 12 3. covariance file (33) added for cross sections below 1 mev. 1303 1451 13 4. angular distributions for mt=105 added below 1 mev. 1303 1451 14 5. radioactive nuclide files added for the production of 6he 1303 1451 15 and tritium. 1303 1451 16 1303 1451 17 ******************************************************************1303 1451 18 1303 1451 19 cross section standard (n,t), thermal to 100 kev. 1303 1451 20 recommended by csewg normalization and standards subcommittee. 1303 1451 21 for a complete description of version iv, see ref.1. 1303 1451 22 1303 1451 23 ******************************************************************1303 1451 24 1303 1451 25 mf=2 --------- resonance parameters ---------------------------- 1303 1451 26 mt=151 effective scattering radius = 2.3778e-13 cm. 1303 1451 27 mf=3 --------- smooth cross sections --------------------------- 1303 1451 28 the 2200 m/s cross sections are as follows, 1303 1451 29 mt=1 sigma = 936.64 barns 1303 1451 30 mt=2 sigma = .71046 barns 1303 1451 31 mt=102 sigma = .03850 barns 1303 1451 32 mt=105 sigma = 935.89 barns 1303 1451 33 1303 1451 34 mt=1,total. below 1 mev, the values are taken from an r-matrix1303 1451 35 analysis by hale,dodder,witte (described in ref.2) which1303 1451 36 takes into account data from all reactions possible in 1303 1451 37 7li up to 3 mev neutron energy. total cross section 1303 1451 38 data considered in this analysis were those of refs. 3 1303 1451 39 and 4. between 1 and 5 mev, the total was taken to be 1303 1451 40 the sum of mt=2,4,24,102,103, and 105, which generally 1303 1451 41 follows the measurements of refs. 5 and 6. between 5 1303 1451 42 and 20 mev, the total was determined by an average of 1303 1451 43 the data of refs. 6 and 7 which agrees with ref. 8 1303 1451 44 except at the lowest energy. in this region, the total 1303 1451 45 exceeds the sum of the measured partial cross sections 1303 1451 46 by as much as 200-300 mb. this difference was distri- 1303 1451 47 buted between the elastic and total (n,nprime)d cross 1303 1451 48 sections. 1303 1451 49 mt=2,elastic. below 3 mev, the values are taken from the 1303 1451 50 r-matrix analysis cited for mt=1, which includes the 1303 1451 51 elastic measurements of refs. 9 and 10. these calcula- 1303 1451 52 tions were matched smoothly in the 3-5 mev region to a 1303 1451 53 curve which lies about 50 mb above bachelor (ref. 26) 1303 1451 54 between 5 and 7.5 mev, and about 13 percent above the 1303 1451 55 data of refs. 14,27,28, and 29 at 10 and 14 mev. 1303 1451 56 mt=4, total inelastic. sum of mt=51 through mt=81. 1303 1451 57 mt=24, (n,2n)alpha. passes through the point of mather and 1303 1451 58 paine (ref.11) at 14 mev, taking into account the 1303 1451 59 measurements of ref. 12. (new measurements by veezer 1303 1451 60 at lasl received after cutoff date.) 1303 1451 61 mt=51,52,54-56,58-81, (n,nprime)d continuum. represented by 1303 1451 62 continuum-level contributions in 6li, binned in .5-mev 1303 1451 63 intervals. the energy-angle spectra are determined by a1303 1451 64 3-body phase-space calculation, assuming isotropic 1303 1451 65 center-of-mass distributions. at each energy, the sum 1303 1451 66 of the continuum-level contributions is normalized to an1303 1451 67 assumed energy-angle integrated continuum cross section 1303 1451 68 which approximates the difference of hopkins measure- 1303 1451 69 ment (ref.13) and the contribution from the first and 1303 1451 70 second levels in 6li. the steep rise of the pseudo- 1303 1451 71 level cross sections from their thresholds and the use 1303 1451 72 of fixed bin widths over finite angles produces ano- 1303 1451 73 molous structure in the individual cross sections 1303 1451 74 which is especially apparent near the thresholds. 1303 1451 75 some effort has been made to smooth out these effects, 1303 1451 76 but they remain to some extent. 1303 1451 77 mt=53, (n,n1)d discrete level. cross section has p-wave 1303 1451 78 penetrability energy dependence from threshold to 3.2 1303 1451 79 mev. matched at higher energies to a curve which lies 1303 1451 80 15-20 per cent above hopkins (ref.13) and passes 1303 1451 81 through the 10 mev point of cookson (ref.14). 1303 1451 82 mt=57, (n,n2)gamma. rises rapidly from threshold, peaks at 1303 1451 83 5 mb and falls off gradually to 20 mev. no data avail- 1303 1451 84 able except upper limits. 1303 1451 85 mt=102, (n,gamma). unchanged from version iv, which was based 1303 1451 86 on the thermal measurement of jurney (ref.15) and the 1303 1451 87 pendlebury evaluation (ref.16) at higher energies. 1303 1451 88 mt=103, (n,p). threshold to 9 mev, based on the data of ref. 1303 1451 89 17. extended to 20 mev through the 14 mev data of 1303 1451 90 refs. 18 and 19. 1303 1451 91 mt=105, (n,t). below 3 mev, values are taken from the r- 1303 1451 92 matrix analysis of ref.2, which includes (n,t) measure- 1303 1451 93 ments from refs 20-24. between 3 and 5 mev, the values 1303 1451 94 are based on bartles measurements (ref.24). 1303 1451 95 at higher energies, the cross sections are taken from 1303 1451 96 the evaluation of ref. 16, extended to 20 mev consider- 1303 1451 97 ing the data of kern (ref.25). 1303 1451 98 mf = 4---------secondary angular distributions-------------------1303 1451 99 mt=2, elastic. legendre coefficients determined as follows. 1303 1451 100 below 2 mev, coefficients up to l=2, were taken from 1303 1451 101 the r-matrix analysis of ref.2, which takes into 1303 1451 102 account elastic angular distribution measurements from 1303 1451 103 refs 9 and 10, above 2 mev, the coefficients represent 1303 1451 104 fits to the measurements of refs 13 and 26 in the 3.5- 1303 1451 105 7-5 mev range, that of ref. 14 at 10 mev, and those of 1303 1451 106 refs. 27-29 at 14 mev. extrapolation of the coefficients1303 1451 107 to 20 mev was aided by optical model calculations. 1303 1451 108 mt=24, (n,2n). lab distributions obtained by integrating 1303 1451 109 over energy the 4-body phase-space spectra that result 1303 1451 110 from transforming isotropic center-of-mass distributions1303 1451 111 to the laboratory system. 1303 1451 112 mt=51-81 (n,nprime). obtained by transforming distributions 1303 1451 113 that are isotropic in the 3-body center-of-mass system 1303 1451 114 to equivalent 2-body distributions in the laboratory 1303 1451 115 system. mt =53 and 57 are treated as real levels and 1303 1451 116 assumed to be isotropic in the two-body reference 1303 1451 117 system. data available indicate departure from isotropy1303 1451 118 for the first real level (mt=53) and this anisotropy 1303 1451 119 will be included in a later update. 1303 1451 120 mt=105 (n,t). legendre coefficients obtained from the r-matrix 1303 1451 121 analysis of ref. 2 are supplied at energies below 1 1303 1451 122 mev. the analysis takes into account (n,t) angular 1303 1451 123 distribution measurements from refs. 23 and 30. 1303 1451 124 mf = 5---------secondary energy distributions--------------------1303 1451 125 mt=24, (n,2n). lab distributions obtained by integrating over 1303 1451 126 angle the 4-body phase-space spectra that result from 1303 1451 127 transforming isotropic center-of-mass distributions to 1303 1451 128 the laboratory system. 1303 1451 129 mf = 8---------radioactive nuclide production--------------------1303 1451 130 mt=103, (n,p). 6he beta decays, with a half-life of 808 ms, 1303 1451 131 back to 6li 100 percent of the time. 1303 1451 132 mt=105, (n,t). tritium, which is the only radioactive product 1303 1451 133 of this reaction, beta decays to 3he 100 percent of the 1303 1451 134 time with a life-time of 12.33 years. 1303 1451 135 mf = 9---------radioactive nuclide multiplicities----------------1303 1451 136 mt=103, (n,p). a multiplicity of one is given for the produc- 1303 1451 137 tion of 6he. 1303 1451 138 mt=105, (n,t). a multiplicity of one is given for the produc- 1303 1451 139 tion of tritium. 1303 1451 140 mf = 12--------gamma-ray multiplicities--------------------------1303 1451 141 mt=57, (n,n2) gamma. energy taken from ref. 31. multiplicity 1303 1451 142 assumed to be one. 1303 1451 143 mt=102, (n,gamma). energies and transition arrays for 1303 1451 144 radiative capture taken from ref. 15, as reported in 1303 1451 145 ref. 31. the lp flag was used to describe the mt=102 1303 1451 146 photons. 1303 1451 147 mf = 14--------gamma-ray angular distributions-------------------1303 1451 148 mt=57, (n,n2)gamma. the gamma is assumed isotropic. 1303 1451 149 mt=102, (n,gamma). the two high-energy gammas are assumed 1303 1451 150 isotropic. data on the 477 kev gamma indicate isotropy. 1303 1451 151 mf=33----------cross section covariances-------------------------1303 1451 152 the relative covariances for mt=1,2, and 105 below 1 mev are 1303 1451 153 given in file 33. they are based on calculations using the co- 1303 1451 154 variances of the r-matrix parameters in first-order error 1303 1451 155 propogation. 1303 1451 156 mt=1,total. relative covariances entered as nc-type sub- 1303 1451 157 subsection, implying that they are to be constructed 1303 1451 158 from those for mt=2 and 105. they are not intended for 1303 1451 159 use at energies above 1.05 mev. 1303 1451 160 mt=2,105,elastic and (n,t). relative covariances among these 1303 1451 161 two cross sections are entered explicitly as ni-type 1303 1451 162 sub-subsections in the lb=5 (direct) representation at 1303 1451 163 energies below 1.05 mev. although values for the .95- 1303 1451 164 1.05 mev bin are repeated in a 1.05-20 mev bin, the 1303 1451 165 covariances are not intended for use at energies 1303 1451 166 above 1.05 mev. 1303 1451 167 1303 1451 168 1303 1451 169 --------------------- references -------------------------------- 1303 1451 170 1303 1451 171 1. g.m.hale, l.stewart, and p.g.young, la-6518-ms (1976). 1303 1451 172 2. g.m.hale, proc, internat. specialists symposium on neutron 1303 1451 173 standards and applications, gaithersburg (1977). 1303 1451 174 3. k.m.diment and c.a.uttley, aere-pr/np 15 and aere-pr/np 16 1303 1451 175 (1969). also private communication to l.stewart. 1303 1451 176 4. j.a.harvey and n.w.hill, proc. conf. on nuclear cross 1303 1451 177 sections and technology, vol.1,244 (1975). 1303 1451 178 5. h.h.knitter, c.budtz-jorgensen, m.mailly, and r.vogt, 1303 1451 179 cbnm-vg (1976). 1303 1451 180 6. c.a.goulding and p.stoler, eandc(us)-176u,161 (1972). 1303 1451 181 7. d.g.foster and d.w.glasgow, phys. rev. c3,576 (1971). 1303 1451 182 8. a.bratenahl, j.m.peterson, and j.p.stoering, phys. rev. 110,1303 1451 183 927 (1958), j.m.peterson, a.bratenahl, and j.p.stoering, 1303 1451 184 phys. rev. 120,521 (1960). 1303 1451 185 9. r.o.lane, ann. phys. 12,135 (1961). 1303 1451 186 10. h.h.knitter and a.m. coppola, eandc(e)-57u (1967). 1303 1451 187 also ref. 5 above. 1303 1451 188 11. d.s.mather and l.f.paine, awre-o-47/69 (1969). 1303 1451 189 12. v.j.ashby et al, phys. rev. 129,1771 (1963). 1303 1451 190 13. j.c.hopkins,d.m.drake, and h.conde, nucl. phys. a107,139 1303 1451 191 (1968), and j.c.hopkins, d.m.drake, and h.conde, la-3765 1303 1451 192 (1967). 1303 1451 193 14. j.a.cookson and d.dandy, nucl. phys. a91,273 (1967). 1303 1451 194 15. e.t.jurney, lasl, private communication (1973). 1303 1451 195 16. e.d.pendlebury, awre-o-60/64 (1964). 1303 1451 196 17. r.bass, c.bindhardt, and k.kruger, eandc(e)-57u (1965). 1303 1451 197 18. g.m.frye, phys. rev. 93,1086 (1954). 1303 1451 198 19. m.e.battat and f.l.ribe, phys.rev. 89,80 (1953). 1303 1451 199 20. m.g.sowerby, b.h.patrick, c.a.uttley, and k.m.diment, 1303 1451 200 j. nucl. energy 24,323 (1970). 6li/10b ratio converted using1303 1451 201 endf/b iv 10b(n,alpha) cross section. 1303 1451 202 21. g.p.lamaze, o.a.wasson,r.a.schrack, and a.d.carlson, proc. 1303 1451 203 internat. conf. on the interactions of neutrons with nuclei,1303 1451 204 vol. 2,1341 (1976). 1303 1451 205 22. w.p.poenitz, z.phys. 268,359 (1974). 1303 1451 206 23. j.c.overley, r.m.sealock, and d.h.ehlers, nucl. phys. a221, 1303 1451 207 573 (1974). 1303 1451 208 24. c.m.bartle, proc. conf. on nuclear cross sections and 1303 1451 209 technology, vol.2,688 (1975), and private communication 1303 1451 210 (1976). 1303 1451 211 25. r.d.kern and w.e.kreger, phys. rev. 112,926 (1958). 1303 1451 212 26. r.batchelor and j.h.towle, nucl. phys. 47,385 (1963). 1303 1451 213 27. a.h.armstrong, j.gammel, l.rosen, and g.m.frye, nucl. phys. 1303 1451 214 52,505 (1964). 1303 1451 215 28. c.wong, j.d.anderson, and j.w.mcclure, nucl. phys. 33,680 1303 1451 216 (1962). 1303 1451 217 29. f.merchez, n.v.sen, v.regis, and r.bouchez, compt. rend. 1303 1451 218 260,3922 (1965). 1303 1451 219 30. i.g.schroder, e.d.mcgarry, g.de leeuw-gierts, and 1303 1451 220 s.de leeuw, proc. conf. on nuclear cross sections and 1303 1451 221 technology, vol.1,240 (1975). 1303 1451 222 31. f.ajzenberg-selove and t.lauritsen, nucl. phys. a227,55 1303 1451 223 (1974). 1303 1451 224 1303 1451 225 1 451 314 11303 1451 226 2 151 4 11303 1451 227 3 1 94 11303 1451 228 3 2 91 11303 1451 229 3 4 46 11303 1451 230 3 24 24 11303 1451 231 3 51 45 11303 1451 232 3 52 43 11303 1451 233 3 53 42 11303 1451 234 3 54 40 11303 1451 235 3 55 37 11303 1451 236 3 56 35 11303 1451 237 3 57 34 11303 1451 238 3 58 30 11303 1451 239 3 59 26 11303 1451 240 3 60 24 11303 1451 241 3 61 23 11303 1451 242 3 62 21 11303 1451 243 3 63 20 11303 1451 244 3 64 19 11303 1451 245 3 65 18 11303 1451 246 3 66 17 11303 1451 247 3 67 16 11303 1451 248 3 68 15 11303 1451 249 3 69 14 11303 1451 250 3 70 13 11303 1451 251 3 71 12 11303 1451 252 3 72 12 11303 1451 253 3 73 11 11303 1451 254 3 74 10 11303 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