Retrieved by E4-util: 2010/02/01,11:42:40 1 0 0 0 4.009300+4 9.210835+1 1 0 59 04093 1451 1 0.000000+0 1.0000E+00 0 0 0 64093 1451 2 1.000000+0 2.0000E+07 0 0 10 04093 1451 3 0.000000+0 0.000000+0 0 0 169 674093 1451 4 40-Zr- 93 IPPE EVAL-JUL06 IGNATYUK A.V. et al. 4093 1451 5 DIST-DEC06 4093 1451 6 ----RUSFOND Material 4093 4093 1451 7 -----Incident neutron data 4093 1451 8 ------ENDF-6 Format 4093 1451 9 4093 1451 10 RUSFOND DESCRIPTION 4093 1451 11 (See RUSFOND manual for details) 4093 1451 12 4093 1451 13 Data from BROND-3 are adopted; changed only number MAT 4093 1451 14 4093 1451 15 **************************************************************** 4093 1451 16 BROND-3 description 4093 1451 17 4093 1451 18 AUTHORS OF EVALUATION: IGNATYUK A.V., MANOKHIN V.N., 4093 1451 19 TERTYCHNY G.Ya. 4093 1451 20 COMPILER OF FILE: BULEEVA N.N. 4093 1451 21 ******************************************************************4093 1451 22 MATERIAL 40-ZR-93 4093 1451 23 ******************************************************************4093 1451 24 Content of file 4093 1451 25 MF = 1 MT = 451 Dictionary and comments 4093 1451 26 MF = 2 MT = 151 Resonance parameters taken from JENDL-3.3. 4093 1451 27 MF = 2 Resonance parameters 4093 1451 28 MT=151 Resolved and unresolved resonance parameters. 4093 1451 29 Resolved region (MLBW formula) : below 6.8 keV 4093 1451 30 Resonance parameters were taken from ENDFF/B-VII based on 4093 1451 31 the measurements of Macklin/85Ma, 86Ma/. 4093 1451 32 A negative resonance was added to reproduce the thermal 4093 1451 33 capture cross section given by Mughabghab et al. /06Mu/. 4093 1451 34 4093 1451 35 Calculated cross section for 2200 m/s (barn): 4093 1451 36 total = 6.460, elastic = 5.765, capture= 0.695 4093 1451 37 Capture resonance iintegral above 0.5 EV : = 17.95 barn. 4093 1451 38 4093 1451 39 Unresolved resonance region : 6.8 KEV - 100 keV 4093 1451 40 Unresolved resonance parameters were adopted from JENDL-3.3. 4093 1451 41 The neutron strength functions, S0, S1 AND S2 were calculated 4093 1451 42 with optical model. The observed level spacing was determined 4093 1451 43 to reproduce the capture cross section experimental data. 4093 1451 44 The effective scattering radius was obtained from fitting to 4093 1451 45 the calculated total cross section 100 KEV. 4093 1451 46 4093 1451 47 Typical values of the parameters at 70 KEV: 4093 1451 48 S0 = 0.370E-4, S1 = 5.480E-4, S2 = 0.360E-4, SG = 5.31E-4, 4093 1451 49 GG = 0.200 EV, R = 6.734 FM. 4093 1451 50 4093 1451 51 MF = 3 Neutron cross section: 4093 1451 52 Neutron cross section in the energy range 0.01-20 MeV were 4093 1451 53 calculated by the GNASH code /96Yo/ modified to take into 4093 1451 54 account the neutron width fluctuations, using aphrouch given 4093 1451 55 in /75Ho/. Neutron transmission coefficients were calculated 4093 1451 56 within the coupled-channel model (code ECIS/70Ra/). 4093 1451 57 Calculations were based on the optical potential /80Ar/, 4093 1451 58 but its surface and volume imaginary potential was modified 4093 1451 59 to take into account direct excitation of the multiplets 4093 1451 60 (5/2+, 2+) x (5/2+,3-). 4093 1451 61 4093 1451 62 Resulting potential parameters are given below: 4093 1451 63 Well depth(MeV) Energy range(MeV) Giometry(fm) 4093 1451 64 Vr=49.0-0.28E 0