IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 33075.0000 74.2780000 0 0 34 103325 1451 1 0.0 0.0 0 0 0 63325 1451 2 1.00000000 60000000.0 0 0 10 20023325 1451 3 300.000000 0.0 1 0 111 43325 1451 4 33-As- 75 FEI EVAL-Sep94 K.I.Zolotarev 3325 1451 5 DIST-May12 Rev.3 May 2012 3325 1451 6 ----IRDF-2002 MATERIAL 3325 3325 1451 7 -----INCIDENT NEUTRON DATA 3325 1451 8 ------ENDF-6 FORMAT 3325 1451 9 ******************************************************************3325 1451 10 IAEA, July 2011 (A. Trkov) 3325 1451 11 Extended cross sections and covariances from 20 to 60 MeV 3325 1451 12 by TENDL-2010, renormalised for continuity. 3325 1451 13 ******************************************************************3325 1451 14 ***************************************************************** 3325 1451 15 ------Russian Reactor Dosimetry File RRDF-2002 3325 1451 16 ***************************************************************** 3325 1451 17 Authors of evaluation: K.Zolotarev, V.Manokhin, A.Pashchenko 3325 1451 18 ***************************************************************** 3325 1451 19 MF=3 3325 1451 20 MT= 16 - As-75(n,2n)As-74 reaction 3325 1451 21 ------------------------------------- 3325 1451 22 Evaluation was made on the base of experimental data [1-18]. 3325 1451 23 Systematics of (n,2n) excitation functions [19] was taken into 3325 1451 24 account in the energy region 10.5 - 13.0 MeV and 19.0 - 20.0 MeV. 3325 1451 25 Cross section data of E.Paul and R.Clarke [20] were rejected 3325 1451 26 due to inconsistency with main bulk of experimental data and 3325 1451 27 systematics of (n,2n) excitation functions. 3325 1451 28 Statistical analysis of input cross section data was carried 3325 1451 29 out by means of PADE-2 code [21]. Rational function was used as 3325 1451 30 the model function [22]. 3325 1451 31 Integral experimental data for U-235 thermal fission neutron 3325 1451 32 spectrum [23-24] was used for testing evaluated As-75(n,2n)As-74 3325 1451 33 excitation function. The results of testing are given in Table 1. 3325 1451 34 Data for U-235 thermal fission neutron spectrum and Cf-252 3325 1451 35 spontaneous fission neutron spectrum were taken from ref.[25] and 3325 1451 36 [26], respectively. 3325 1451 37 Table 1. 3325 1451 38 ---------------------------------------------------------------- 3325 1451 39 TYPE OF SPECTRUM I ,mb (calc.) I , mb (measured) 3325 1451 40 ---------------------------------------------------------------- 3325 1451 41 U-235 neutron fission I 0.29430 I 0.304 +- 0.036 [22] 3325 1451 42 I I 0.311 +- 0.023 [23] 3325 1451 43 ---------------------------------------------------------------- 3325 1451 44 Cf-252 spont. fission I 0.62091 I 3325 1451 45 ---------------------------------------------------------------- 3325 1451 46 3325 1451 47 MT=33 3325 1451 48 MT= 16 -(n,2n) cross section cov. matrix 3325 1451 49 ---------------------------------------- 3325 1451 50 Uncertainties in the evaluated excitation function for the 3325 1451 51 reaction As-75(n,2n)As-74 are given in the form of relative cova- 3325 1451 52 riance matrix for the 19-neutron energy groups (LB=5). Covariance 3325 1451 53 matrix of uncertainties was calculated simultaneously with 3325 1451 54 recommended cross section data by means of PADE-2 code. 3325 1451 55 Eigenvalues of the 6-th digits relative covariance matrix 3325 1451 56 given in the 33-file are the following: 3325 1451 57 3325 1451 58 5.35971E-06 5.38799E-06 5.42397E-06 5.50786E-06 3325 1451 59 5.57389E-06 5.75522E-06 6.10958E-06 6.70182E-06 3325 1451 60 7.72263E-06 9.64519E-06 1.38994E-05 2.65454E-05 3325 1451 61 9.61963E-05 2.33816E-03 3.36728E-03 3.72580E-03 3325 1451 62 1.03166E-02 1.50199E-02 9.08387E-02 3325 1451 63 3325 1451 64 References : 3325 1451 65 1. R.J.Prestwood, B.P.Bayhurst, Phys. Rev., v.121, p.1438, 1961 3325 1451 66 2. B.Granger, M.Longueve, Report EANDC(E)-49L, p.83, Oct. 1963 3325 1451 67 3. P.Hille, H.Muenzer,Acta Phys. Austriaca, v.23, p.44, May 1966 3325 1451 68 4. J.Csikai, G.Peto, Acta Physica Hung., v.23, p.87, May 1967 3325 1451 69 5. M.Bormann et al., Nucl. Phys., v.A115, p.309, July 1968 3325 1451 70 M.Bormann et al., Progress Report EANDC(E)-76, January 1967 3325 1451 71 6. P.R.Prasad et al., Nucl. Phys., v.A138, p.85, November 1969 3325 1451 72 7. P.Venugopala Rao et al., Phys. Rev., v.C3, p.629, Feb. 1971 3325 1451 73 8. M.Wagner, M.Uhl, Oesterr. Akad. Wiss., Math.+Naturw. Anzeiger,3325 1451 74 v.108, p.185, November 1971 3325 1451 75 9. S.M.Qaim, Nucl. Phys., Sec.A, v.185, p.614, May 1972 3325 1451 76 10. D.V.Viktorov, V.L.Sjablin,Jadernaja Fizika, v.15,p.1099, 1972 3325 1451 77 11. C.T.Simpson et al.,Inorg. Nucl. Chem., v.35, p.2085,June 1973 3325 1451 78 12. J.Araminowicz,J.Dresler Peport INR-1464, Warsaw,p.14,May 1973 3325 1451 79 13. W.Grochulski et al., Acta Physica Polonica, v.B6,p.139, 1975 3325 1451 80 14. R.A.Sigg, Dissertation Abstract, sec.B, v.37,p.2237, Nov.1976 3325 1451 81 15. J.L.Casanova,M.L.Sanchez, Anales de Fisica y Quimica (Spain), 3325 1451 82 v.72, n.3, p.186, July 1976 3325 1451 83 16. S.Sothras, Dissertation Abstract, sec.B,v.38,p.280, July 1978 3325 1451 84 17. C.Konno, Y.Ikeda, K.Oishi e.a., Report JAERI-1329, Oct. 1993 3325 1451 85 18. I.Birn, S.M.Qaim, Nucl. Sci. Eng., v.116, p.125-137, 1994 3325 1451 86 19. V.N.Manokhin, VANT, Ser.:Yadernye Konstanty, 1994, No. 1, 3325 1451 87 pp.18-22 3325 1451 88 20. E.B.Paul, R.L.Clarke, Can. J. Phys., v.31, p.267, 1953 3325 1451 89 21. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 3325 1451 90 22. S.Badikov, N.Rabotnov, K.Zolotarev, Proc. of NEANSC Speciali- 3325 1451 91 st's Meeting on Evaluation and Processing of Covariance Data, 3325 1451 92 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 3325 1451 93 23. F.Nasyrov, B.D.Sciborskij, Atomnaja Energija, v.25, no.5, 3325 1451 94 p.437, November 1968 3325 1451 95 24. E.Steinnes, Radiochimica Acta, v.13, p.169, June 1970 3325 1451 96 25. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 3325 1451 97 Library, MAT=9228, MF=5, MT=18, eval. April 1989 3325 1451 98 26. W.Mannhart, Report INDC(NDS)-220/L,p.158, IAEA, Vienna, 1989 3325 1451 99 ***************************************************************** 3325 1451 100 The Q values and threshold energies were updated prior to pro- 3325 1451 101 cessing through the codes to comply with the values obtained 3325 1451 102 using the NNDC calculation program which is based on the 1995 3325 1451 103 Update to the Atomic mass Evaluation. 3325 1451 104 3325 1451 105 File 2 added to the pointwise file containing only the effective 3325 1451 106 scattering radius with no resonance parameters given. 3325 1451 107 Taken from ENDF/B-VI 3325 1451 108 ***************************************************************** 3325 1451 109 ***************** Program LINEAR (VERSION 2012-1) ***************3325 1451 110 For All Data Greater than 1.0000D-10 barns in Absolute Value 3325 1451 111 Data Linearized to Within an Accuracy of .100000000 per-cent 3325 1451 112 ***************** Program GROUPIE (VERSION 2012-1) **************3325 1451 113 Unshielded Group Averages Using 640 Groups 3325 1451 114 Weighting Spectrum: Flat (Constant) Spectrum 3325 1451 115 1 451 108 13325 1451 116 2 151 4 13325 1451 117 3 16 45 13325 1451 118 33 16 49 13325 1451 119 3325 1 0 120 3325 0 0 121 33075.0000 74.2780000 0 0 1 03325 2151 122 3.307500+4 1.000000+0 0 0 1 03325 2151 123 1.000000-5 2.405300+3 0 0 0 03325 2151 124 1.500000+0 5.086300-1 0 0 0 03325 2151 125 3325 2 0 126 3325 0 0 127 33075.0000 74.2780000 0 0 0 03325 3 16 128 -10243800.0-10243800.0 0 0 1 983325 3 16 129 98 1 3325 3 16 130 10300000.0 6.29473E-6 10400000.0 6.09023E-4 10500000.0 .0052550513325 3 16 131 10600000.0 .014392211 10700000.0 .028074850 10800000.0 .0460172503325 3 16 132 10900000.0 .067864400 11000000.0 .093207450 11100000.0 .1216010003325 3 16 133 11200000.0 .152580000 11300000.0 .185675000 11400000.0 .2204260003325 3 16 134 11500000.0 .256394000 11600000.0 .293170500 11700000.0 .3303835003325 3 16 135 11800000.0 .367700500 11900000.0 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15700000.0 1.11461000 15800000.0 1.11977000 15900000.0 1.124580003325 3 16 149 16000000.0 1.12905000 16100000.0 1.13319500 16200000.0 1.137030003325 3 16 150 16300000.0 1.14056500 16400000.0 1.14381000 16500000.0 1.146775003325 3 16 151 16600000.0 1.14947500 16700000.0 1.15192000 16800000.0 1.154110003325 3 16 152 16900000.0 1.15605500 17000000.0 1.15777000 17100000.0 1.159255003325 3 16 153 17200000.0 1.16051000 17300000.0 1.16155000 17400000.0 1.162380003325 3 16 154 17500000.0 1.16299500 17600000.0 1.16340500 17700000.0 1.163620003325 3 16 155 17800000.0 1.16363500 17900000.0 1.16345500 18000000.0 1.163085003325 3 16 156 18100000.0 1.16252000 18200000.0 1.16177000 18300000.0 1.160830003325 3 16 157 18400000.0 1.15970000 18500000.0 1.15839000 18600000.0 1.156890003325 3 16 158 18700000.0 1.15520000 18800000.0 1.15333000 18900000.0 1.151270003325 3 16 159 19000000.0 1.14901500 19100000.0 1.14657000 19200000.0 1.143935003325 3 16 160 19300000.0 1.14110500 19400000.0 1.13807000 19500000.0 1.134835003325 3 16 161 19600000.0 1.13139500 19700000.0 1.12774000 19800000.0 1.123870003325 3 16 162 19900000.0 1.12048000 20000000.0 0.0 3325 3 16 163 3325 3 0 164 3325 0 0 165 33075.0000 74.2780000 0 0 0 1332533 16 166 0.000000+0 0.000000+0 0 16 0 2332533 16 167 0.000000+0 0.000000+0 1 5 36 8332533 16 168 1.000000-5 2.000000+7 2.400000+7 2.800000+7 3.400000+7 4.200000+7332533 16 169 5.000000+7 6.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0332533 16 170 0.000000+0 0.000000+0 0.000000+0 1.884940-3 4.401760-3 5.343790-3332533 16 171 4.921050-3 4.805040-3 4.252840-3 1.473940-2 1.906700-2 1.760470-2332533 16 172 1.699710-2 1.481890-2 2.506560-2 2.324140-2 2.253650-2 1.967270-2332533 16 173 2.168760-2 2.112060-2 1.858590-2 2.070990-2 1.830970-2 1.651660-2332533 16 174 0.000000+0 0.000000+0 1 5 231 21332533 16 175 1.000000-5 1.038170+7 1.100000+7 1.150000+7 1.200000+7 1.250000+7332533 16 176 1.300000+7 1.350000+7 1.400000+7 1.450000+7 1.500000+7 1.550000+7332533 16 177 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