Russian Reactor Dosimetry File RRDF-98 .220490E+05 4.85791+ 1 0 0 41 02242 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 62242 1451 2 1.00000+ 0 0.00000+ 0 0 0 10 22242 1451 3 0.00000+ 0 0.00000+ 0 0 0 55 32242 1451 4 22-TI-49 FEI EVAL-Nov93 K.Zolotarev and A.Pashchenko 2242 1451 5 DIST-Dec93 2242 1451 6 ---RRDF-98 MATERIAL 2242 2242 1451 7 ----INCIDENT NEUTRON DATA 2242 1451 8 -----ENDF-6 FORMAT 2242 1451 9 ***************************************************************** 2242 1451 10 -----DOSIMETRY FILE 2242 1451 11 ***************************************************************** 2242 1451 12 AUTHORS OF EVALUATION: K.Zolotarev and A.Pashchenko 2242 1451 13 ***************************************************************** 2242 1451 14 2242 1451 15 MF= 3 2242 1451 16 MT=28 -(n,x) cross section 2242 1451 17 --------------------------------------- 2242 1451 18 Evaluation include sum of the reactions Ti49(n,np)Sc48, 2242 1451 19 Ti49(n,pn)Sc48, Ti49(n,d)Sc48 excitation functions. 2242 1451 20 Evaluation of Ti49(n,x)Sc48 excitation function is based on 2242 1451 21 the experimental data [1- 5]. Old experimental data were renorma- 2242 1451 22 lized to the new standard data. The final procedure of evaluation 2242 1451 23 was carried out by means of of Pade-approximation calculation [6] 2242 1451 24 ( L=6, SUM1=1.5228 , ZED =0.50). 2242 1451 25 The energy dependence of cross-section from 12.00 MeV to 2242 1451 26 threshold was extrapolated with linear function. 2242 1451 27 U-235 thermal fission [7] and Cf-252 spontanious fission 2242 1451 28 neutron spectra [8] averaged cross-sections calculated from the 2242 1451 29 evaluated Ti49(n,x)Sc48 exitation function are the following: 2242 1451 30 2242 1451 31 --------------------------------------------------------------- 2242 1451 32 TYPE OF SPECTRUM I ,mb (calc.) I , mb (measured) 2242 1451 33 ----------------------I-----------------I---------------------- 2242 1451 34 U-235 neutron fission I I 2242 1451 35 I I 2242 1451 36 ----------------------I-----------------I---------------------- 2242 1451 37 CF-252 spont. fission I I 2242 1451 38 2242 1451 39 MF=33 2242 1451 40 MT=28 -(n,x) cross section cov. matrix 2242 1451 41 --------------------------------------- 2242 1451 42 The covarience matrix of cross section uncertainties were 2242 1451 43 obtained simultaneously with (n,x) excitation function by means 2242 1451 44 of PADE-2 code in the LB=5 representation. 2242 1451 45 2242 1451 46 References : 2242 1451 47 1. W.G.Cross,H.L.Pai Progress Rep. EANDC(CAN)-16, p.1, Jan.1963 2242 1451 48 2. H.L.Pai Canadian J. of Physics, v.44, p.2337, 1966 2242 1451 49 3. S.M.Qaim Nucl.Phys., v.A382, n.2, p.255, July 1982 2242 1451 50 4. I.Ribansky,S.Gmuca J.,Phys.G, v.9, p.1537, Dec.1983 2242 1451 51 5. Y.Ikeda e.a. Report JAERI-1312, 1988 2242 1451 52 6. S.A.Badikov et.al. Preprint FEI-1686, Obninsk, 1985 2242 1451 53 7. L.W.Weston e.a. Evaluated Neutron Data for U-235, ENDF/B-VI 2242 1451 54 Library, MAT=9228, MF=5, MT=18, eval.apr. 1989 2242 1451 55 8. W.Mannhart IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987 2242 1451 56 2242 1451 57 ***************************************************************** 2242 1451 58 2242 1451 59 1 451 62 02242 1451 60 3 28 32 02242 1451 61 33 28 23 02242 1451 62 2242 1 0 63 2242 0 0 64 2.20490+ 4 4.85791+ 1 0 0 0 02242 3 28 65 0.00000+ 0-9.12956+ 6 0 0 1 852242 3 28 66 85 2 2242 3 28 67 9.31749+ 6 0.00000+ 0 1.17000+ 7 3.99987- 5 1.18000+ 7 4.54851- 52242 3 28 68 1.19000+ 7 5.72022- 5 1.20000+ 7 7.57969- 5 1.21000+ 7 1.01961- 42242 3 28 69 1.22000+ 7 1.36433- 4 1.23000+ 7 1.79999- 4 1.24000+ 7 2.33489- 42242 3 28 70 1.25000+ 7 2.97783- 4 1.26000+ 7 3.73801- 4 1.27000+ 7 4.62509- 42242 3 28 71 1.28000+ 7 5.64905- 4 1.29000+ 7 6.82021- 4 1.30000+ 7 8.14919- 42242 3 28 72 1.31000+ 7 9.64672- 4 1.32000+ 7 1.13237- 3 1.33000+ 7 1.31908- 32242 3 28 73 1.34000+ 7 1.52587- 3 1.35000+ 7 1.75377- 3 1.36000+ 7 2.00375- 32242 3 28 74 1.37000+ 7 2.27672- 3 1.38000+ 7 2.57349- 3 1.39000+ 7 2.89476- 32242 3 28 75 1.40000+ 7 3.24109- 3 1.41000+ 7 3.61289- 3 1.42000+ 7 4.01039- 32242 3 28 76 1.43000+ 7 4.43361- 3 1.44000+ 7 4.88234- 3 1.45000+ 7 5.35615- 32242 3 28 77 1.46000+ 7 5.85437- 3 1.47000+ 7 6.37606- 3 1.48000+ 7 6.92002- 32242 3 28 78 1.49000+ 7 7.48481- 3 1.50000+ 7 8.06875- 3 1.51000+ 7 8.66994- 32242 3 28 79 1.52000+ 7 9.28627- 3 1.53000+ 7 9.91549- 3 1.54000+ 7 1.05552- 22242 3 28 80 1.55000+ 7 1.12028- 2 1.56000+ 7 1.18559- 2 1.57000+ 7 1.25119- 22242 3 28 81 1.58000+ 7 1.31682- 2 1.59000+ 7 1.38224- 2 1.60000+ 7 1.44721- 22242 3 28 82 1.61000+ 7 1.51152- 2 1.62000+ 7 1.57496- 2 1.63000+ 7 1.63735- 22242 3 28 83 1.64000+ 7 1.69853- 2 1.65000+ 7 1.75835- 2 1.66000+ 7 1.81671- 22242 3 28 84 1.67000+ 7 1.87350- 2 1.68000+ 7 1.92866- 2 1.69000+ 7 1.98214- 22242 3 28 85 1.70000+ 7 2.03391- 2 1.71000+ 7 2.08397- 2 1.72000+ 7 2.13231- 22242 3 28 86 1.73000+ 7 2.17896- 2 1.74000+ 7 2.22397- 2 1.75000+ 7 2.26737- 22242 3 28 87 1.76000+ 7 2.30924- 2 1.77000+ 7 2.34963- 2 1.78000+ 7 2.38863- 22242 3 28 88 1.79000+ 7 2.42631- 2 1.80000+ 7 2.46276- 2 1.81000+ 7 2.49807- 22242 3 28 89 1.82000+ 7 2.53232- 2 1.83000+ 7 2.56561- 2 1.84000+ 7 2.59803- 22242 3 28 90 1.85000+ 7 2.62967- 2 1.86000+ 7 2.66061- 2 1.87000+ 7 2.69096- 22242 3 28 91 1.88000+ 7 2.72078- 2 1.89000+ 7 2.75018- 2 1.90000+ 7 2.77923- 22242 3 28 92 1.91000+ 7 2.80802- 2 1.92000+ 7 2.83661- 2 1.93000+ 7 2.86510- 22242 3 28 93 1.94000+ 7 2.89356- 2 1.95000+ 7 2.92206- 2 1.96000+ 7 2.95067- 22242 3 28 94 1.97000+ 7 2.97946- 2 1.98000+ 7 3.00850- 2 1.99000+ 7 3.03787- 22242 3 28 95 2.00000+ 7 3.06762- 2 2242 3 28 96 2242 3 0 97 2242 0 0 98 2.20490+ 4 4.85791+ 1 0 0 0 1224233 28 99 0.00000+ 0 0.00000+ 0 0 28 0 1224233 28 100 0.00000+ 0 0.00000+ 0 1 5 120 15224233 28 101 9.31749+ 6 1.17000+ 7 1.25000+ 7 1.30000+ 7 1.35000+ 7 1.40000+ 7224233 28 102 1.45000+ 7 1.50000+ 7 1.55000+ 7 1.60000+ 7 1.65000+ 7 1.70000+ 7224233 28 103 1.80000+ 7 1.90000+ 7 2.00000+ 7 0.00000+ 0 0.00000+ 0 0.00000+ 0224233 28 104 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0224233 28 105 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 6.15308- 1224233 28 106 2.04375- 1 5.17348- 2-1.34870- 3-9.45196- 3 7.73782- 5 1.10779- 2224233 28 107 1.46519- 2 8.42412- 3-4.85248- 3-2.57995- 2-3.10664- 2 8.46126- 3224233 28 108 9.03048- 2 3.72868- 2 1.39630- 2 4.69690- 3 2.65788- 3 3.81084- 3224233 28 109 5.52158- 3 6.29876- 3 5.69412- 3 2.90245- 3-5.46626- 4-2.21892- 4224233 28 110 2.64780- 2 1.74712- 2 1.04765- 2 5.35173- 3 2.28815- 3 1.22146- 3224233 28 111 1.69474- 3 2.97260- 3 4.67782- 3 4.12675- 3-1.15426- 3 1.59940- 2224233 28 112 1.20453- 2 7.38276- 3 3.11263- 3 4.07752- 5-1.51130- 3-1.71149- 3224233 28 113 -5.29294- 4 8.96322- 4-9.08016- 5 1.10776- 2 8.40890- 3 4.87297- 3224233 28 114 1.23561- 3-1.81646- 3-3.85447- 3-4.69471- 3-2.92602- 3 8.69483- 4224233 28 115 8.20144- 3 6.72165- 3 4.29212- 3 1.45638- 3-1.17031- 3-3.60461- 3224233 28 116 -3.37277- 3 8.97681- 4 8.05708- 3 8.50602- 3 8.01846- 3 6.79372- 3224233 28 117 4.28825- 3 1.40094- 3 1.03950- 5 1.29221- 2 1.65348- 2 1.86024- 2224233 28 118 1.78779- 2 1.11442- 2-1.09132- 3 2.50005- 2 3.14348- 2 3.39521- 2224233 28 119 2.38144- 2-1.32299- 3 4.21638- 2 4.85333- 2 3.65196- 2 3.67227- 4224233 28 120 5.97504- 2 4.96005- 2 8.51172- 3 5.01907- 2 2.91276- 2 6.17145- 2224233 28 121 224233 0 122 2242 0 0 123 0 0 0 124 -1 0 0 124