Russian Reactor Dosimetry File RRDF-98 .260540E+05 5.34765+ 1 0 0 41 12613 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 62613 1451 2 1.00000+ 0 0.00000+ 0 0 0 10 22613 1451 3 0.00000+ 0 0.00000+ 0 0 0 95 32613 1451 4 26-FE-54 FEI EVAL-Aug98 2613 1451 5 DIST-Oct98 2613 1451 6 ---HEND MATERIAL 2613 2613 1451 7 ----INCIDENT NEUTRON DATA 2613 1451 8 -----ENDF-6 FORMAT 2613 1451 9 ***************************************************************** 2613 1451 10 -----Data file for high energy neutron dosimetry 2613 1451 11 ***************************************************************** 2613 1451 12 AUTHORS OF EVALUATION: K.Zolotarev, M.Scripova,A.Pashchenko 2613 1451 13 ***************************************************************** 2613 1451 14 MF=3 2613 1451 15 MT= 16 -(n,2n) cross section 2613 1451 16 ------------------------------------- 2613 1451 17 Excitation function for the Fe-54(n,2n)Fe-53m+g reaction in 2613 1451 18 the energy region from threshold to 21 MeV was evaluated by means 2613 1451 19 of statistical analysis of experimental cross section data [1-16] 2613 1451 20 and data from GNASH calculation. 2613 1451 21 All experimental data were renormalized to the new standards 2613 1451 22 for monitor reactions cross sections and decay data.Cross section 2613 1451 23 data for the monitor reaction Al-27(n,p)Mg-27 were taken from new 2613 1451 24 re-evaluation [17]. Terrel et al. data [1] mesured at 16.89 and 2613 1451 25 17.89 MeV have been corrected introducing the Fc=0.5 coefficient, 2613 1451 26 because authors used double decreased value for positron yield. 2613 1451 27 Andreev et al. data [6] have been renormalized using preliminary 2613 1451 28 evaluated integral cross section value in the neutron energy 2613 1451 29 range from 15.0 to 16.5 MeV. Renormalised experimental data by 2613 1451 30 Andreev et al. are well consistent with Ryves [9-10] mesurement 2613 1451 31 results and with new experimental data for Fe-54(n,2n)Fe-53m+g 2613 1451 32 reaction measured by Fessler [16]. 2613 1451 33 Experimental data from ref.[18-26] were rejected due to their 2613 1451 34 discrepancy with the main bulk of experimental data [1-16] and 2613 1451 35 data from theoretical model calculation. 2613 1451 36 The final procedure of evaluation Fe54(n,2n)Fe53m+g excitati- 2613 1451 37 on function from threshold to 21 MeV has been carried out within 2613 1451 38 the framework of generalized least squares method. Rational func- 2613 1451 39 tion was used as model function [27]. 2613 1451 40 U-235 thermal fission [28] and Cf-252 spontanious fission 2613 1451 41 neutron spectra [29] averaged cross sections calculated from the 2613 1451 42 evaluated Fe54(n,2n)Fe53m+g exitation function are the following: 2613 1451 43 2613 1451 44 -------------------------------------------- 2613 1451 45 TYPE OF SPECTRUM I , mb (calc.) 2613 1451 46 --------------------------I----------------- 2613 1451 47 U-235 neutron fission I 1.2839E-3 2613 1451 48 CF-252 spontan. fission I 3.6219E-3 2613 1451 49 2613 1451 50 MF=33 2613 1451 51 MT= 16 -(n,2n) cross section cov. matrix 2613 1451 52 ------------------------------------------- 2613 1451 53 The covariance matrix of cross section uncertainties were 2613 1451 54 obtained simultaneously with (n,2n) excitation function by means 2613 1451 55 of PADE-2 code in the LB=5 representation. 2613 1451 56 2613 1451 57 REFERENCES : 2613 1451 58 1. J.Terrell,D.M.Holm Physical Review, v.109, p.2031, 1958 2613 1451 59 2. M.J.Depraz et al. Journal de Physique, v.21, p.377, May 1960 2613 1451 60 3. D.M.Chittenden et al. Physical Review, v.122, p.860, 1961 2613 1451 61 4. W.G.Cross et al. Prog. Report EANDC(CAN)-16, p., January 1963 2613 1451 62 5. S.R.Salisbury, R.A.Chalmers Phys. Rev., v.B140, p.305, 1965 2613 1451 63 6. M.F.Andreev, V.I.Serov Jadernaja Fizika (Sov.), v.7, n.4, 2613 1451 64 p.745, April 1968 2613 1451 65 7. S.M.Qaim Nuclear Physics, v.A185, p.614, May 1972 2613 1451 66 8. R.A.Sigg,P.K.Kuroda Inorg. Nucl. Chem., v.37, p.631, Mar.1975 2613 1451 67 9. T.B.Ryves et al. J. Metrologia, v.14, n.3, p.127, June 1978 2613 1451 68 10. T.B.Ryves et al. J. of Physics, pt.G, v.4, n.11, p.1783, 1978 2613 1451 69 11. B.M.Bahal, R.Pepelink Report GKSS-84-E-, 1984 2613 1451 70 12. L.R.Greenwood, R.K.Smither Proc. of Int. Conf. Nuclear Data 2613 1451 71 for Basic and Applied Science, Santa Fe, New Mexico, USA, 2613 1451 72 13-17 May 1985, v.1, p.163 2613 1451 73 13. T.Katoh et al. Report JAERI-M-89-083, 1989 2613 1451 74 14. M.Viennot et al. Nucl. Sci. Eng., v.108, p.289, July 1991 2613 1451 75 15. A.Ercan et al. Proc. of an Intern. Conf. on Nuclear Data for 2613 1451 76 Science and Technology, 13-17 May 1991, Julich, FRG, Springer-2613 1451 77 Verlag, 1992 2613 1451 78 16. A.Fessler Report JUL-3502, FZ Julich GmbH, Germany, 1998 2613 1451 79 17. K.I.Zolotarev et al. Private communication, Obninsk, 1998 2613 1451 80 18. D.L.Allan J,Proc.Phys.Soc., v.70, p.195, 1956 2613 1451 81 19. L.A.Rayburn Phys. Rev., v.122, p.168, 1961 2613 1451 82 20. H.Pollehn, H.Neuert Zeitschrift f. Naturforschung, sect.A, 2613 1451 83 v.16, p.227,1961 2613 1451 84 21. C.Carles Comptes Rendus, v.257, p.659, July 1963 2613 1451 85 22. J.Csikai Report EANDC-50S, v.2, p.102, July 1965 2613 1451 86 23. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 2613 1451 87 24. J.Araminowicz, J.Dresler Rep.INR-1464, Swierk-Warsew,May 1973 2613 1451 88 25. M.Bormann et al. Zeitsch. f. Physik, sect.A, v.277, p.203, 2613 1451 89 June 1976 2613 1451 90 26. Zhou Muyao et.al. Chinese J. of Nucl.Phys., v.9, p.34, 1987 2613 1451 91 27. S.Badikov, K.Zolotarev Proc. of NEANSC Specialist's. Meeting 2613 1451 92 on Evaluation and Processing of Covariance Data, Oar Ridge , 2613 1451 93 USA, 1992, OECD, Paris, 1993, p.105 2613 1451 94 28. L.W.Weston e.a. Evaluated Neutron Data for U-235, ENDF/B-VI 2613 1451 95 Library, MAT=9228, MF=5, MT=18, eval.apr. 1989 2613 1451 96 29. W.Mannhart IAEA-TECDOC-410, p.158, 1987 2613 1451 97 *************************************************************** 2613 1451 98 2613 1451 99 1 451 102 12613 1451 100 3 16 29 12613 1451 101 33 16 35 12613 1451 102 2613 1 0 103 2613 0 0 104 2.60540+ 4 5.34762+ 1 0 0 0 02613 3 16 105 -1.33800+ 0-1.33800+ 7 0 0 1 762613 3 16 106 76 2 2613 3 16 107 0.00000+ 0 0.00000+ 0 1.36280+ 7 1.50076- 4 1.37000+ 7 2.12743- 42613 3 16 108 1.38000+ 7 3.90988- 4 1.39000+ 7 6.81009- 4 1.40000+ 7 1.08872- 32613 3 16 109 1.41000+ 7 1.61952- 3 1.42000+ 7 2.27811- 3 1.43000+ 7 3.06838- 32613 3 16 110 1.44000+ 7 3.99327- 3 1.45000+ 7 5.05464- 3 1.46000+ 7 6.25319- 32613 3 16 111 1.47000+ 7 7.58830- 3 1.48000+ 7 9.05801- 3 1.49000+ 7 1.06590- 22613 3 16 112 1.50000+ 7 1.23864- 2 1.51000+ 7 1.42342- 2 1.52000+ 7 1.61947- 22613 3 16 113 1.53000+ 7 1.82594- 2 1.54000+ 7 2.04184- 2 1.55000+ 7 2.26609- 22613 3 16 114 1.56000+ 7 2.49752- 2 1.57000+ 7 2.73494- 2 1.58000+ 7 2.97708- 22613 3 16 115 1.59000+ 7 3.22267- 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5.31401- 3 7.81331- 3 261333 16 170 261333 0 171 2613 0 0 172 0 0 0 173 -1 0 0 173