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71-Lu-175 ORNL,BNW EVAL-MAR98 R.Q. WRIGHT, LEONARD-STEWART DIST-JAN09 20090105 ----JEFF-311 MATERIAL 7125 REVISION 1 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT *************************** JEFF-3.1.1 ************************* ** ** ** Original data taken from: JEFF-3.1 ** ** ** ****************************************************************** ***************************** JEFF-3.1 ************************* ** ** ** Original data taken from: ENDF/B-VI.8 ** ** ** ****************************************************************** ***************************************************************** ENDF/B-VI MOD 1 Revision, March 1998, R.Q. Wright (ORNL) This revision contains the following changes, relative to the 1967 evaluation: MF= 2 RESONANCE PARAMETERS RESOLVED RESONANCE RANGE 1.0E-5 to 411.0 eV (revised) The resolved resonance parameters are taken from Mughabghab [24]. A MLBW formalism is used. UNRESOLVED RESONANCE RANGE 411 eV to 10 keV (revised) The scattering radius, R = 7.7 fm. MF=3 SMOOTH CROSS SECTIONS Total, elastic, and capture are set to zero below 10 keV. The capture cross-section (MT = 102) is revised for the 10 keV to 20 MeV energy range, based on data of Macklin [23]. Scattering cross-section is revised to reflect the change in the capture and to keep the total cross-section unchanged. Table 1. Lu-175 Average Capture (mb) Energy (keV) Evaluation Macklin [23] Flat wt. 3 - 4 4816 5159 4 - 5 4036 4170 5 - 6 3547 3360 6 - 8 3035 2997 8 -10 2595 2545 10 -12 2260 2171 12 -15 1988 1956 15 -18 1761 1724 18 -21 1600 1583 21 -25 1455 1446 25 -30 1315 1279 30 -35 1205 1192 35 -45 1093 1072 45 -55 985.8 986 55 -65 907.7 899 65 -80 834.3 824 80-100 756.4 749 100-120 695.0 700 120-150 615.2 611 150-180 543.0 545 +/- 4 180-210 497.5 495 +/- 4 210-250 464.9 462 +/- 3 250-300 432.7 433 +/- 3 300-350 392.4 397 +/- 3 350-400 342.7 339 +/- 3 400-450 291.8 293 +/- 3 450-500 249.1 246 +/- 3 500-550 218.8 223 +/- 3 550-600 198.8 195 +/- 3 600-650 184.4 185 +/- 3 650-700 172.2 171 +/- 3 700-750 161.9 164 +/- 3 750-800 154.2 152 +/- 3 800-850 148.2 149 +/- 3 850-900 143.2 143 +/- 3 900-950 139.7 133 +/- 3 950-1000 136.5 135 +/- 3 1000-1100 132.6 135 +/- 3 1100-1200 128.1 126 +/- 3 1200-1300 124.4 126 +/- 3 1300-1400 121.4 125 +/- 3 1400-1500 119.2 125 +/- 3 1500-1600 117.7 118 +/- 4 1600-1700 116.7 120 +/- 4 1700-1800 116.2 115 +/- 4 1800-1900 115.5 117 +/- 5 1900-2000 114.5 127 +/- 5 2200 m/s cross sections (barns) Evaluation Macklin [23] Total 29.52 30.2 Elastic 6.44 7.1 +/- 0.4 Capture 23.08 23.1 +/- 1.1 Capture resonance integral (barns) Evaluation Macklin [23] 0.5 - 411 eV 590.40 0.411 - 10 keV 27.25 10 keV - 4.15 Total RI 621.80 610.0 +/- 50 ***************************************************************** ENDF/B-VI MOD 0, February 1990 (NNDC) ENDF/B-V material converted to ENDF-6 format by NNDC. ***************************************************************** ENDF/B-V Evaluation, MAT 1302, June 1967, B.R. Leonard and K.B. Stewart (BNW) This file transfered from ENDF/B-III with no modifications. Data modified June, 1970 to conform to ENDF/B-II formats MF= 1 GENERAL INFORMATION MT=451 Atomic mass=174.9409 I=3.5 from Chart of Nuclides [2] MT=453 Radioactive decay for MT=16,17,102,103,107 [2] MF= 3 SMOOTH CROSS SECTIONS MT= 1 Total at 0.0001 eV to 1.0 eV calculated by UNICORN [10] for 0 K using parameters of File 2 to fit [1] the data of Baston [8], 31.14 barns at 0.0253 eV. 10 keV to 20 MeV: 10 keV to 2.5 MeV total similar to erbium and hafnium; 2.5 to 15 MeV eye fit to data of Otter [11]. 15 to 20 MeV Optical-Model calculations [1] using ABACUS-2 [12]. MT= 2 Elastic scattering 0.0001 eV to 1.0 eV from UNICORN calculation [1]. No Bragg effects. 10 keV to 20 MeV by subtraction of all others from total. MT= 4 Inelastic scattering from ABACUS calculation [1]. MT= 16,17 Threshold to 20 MeV Calculated [1] by procedure of Pearlstein [13]. MT=102 Capture 0.0001 eV to 1.0 eV from UNICORN calculation [1], 25.88 barns at 0.0253 eV. 10 keV to 20 MeV: 10-20 keV extrapolation of data Block [14], 24 keV Chaubey [15], 30-200 keV Macklin [16], 14 MeV Kenna [17]. MT=103 n,p constructed to pass [1] experimental value 14 MeV Coleman [18]. MT=107 n,alpha shape as 197Au (ENDF/B) passing through 14 MeV value of Marcazzan [19]. MF= 4 LEGENDRE POLYNOMIALS MT= 2 20 by 20 transformation matrix c.m.-lab calculated [1] by CHAD. 19 c.m. Legendre coefficients 10 keV to 20 MeV calculated from distributions of ABACUS [1] by modified version [1] of CHAD. No compound-elastic for E > 5. MeV. MF= 5 SECONDARY ENERGY DISTRIBUTIONS MT= 4 Inelastic scattering threshold to 2.0 MeV to 8 levels [21] from Hausser Feshbach ABACUS calculation [1]. 2-20 MeV nuclear temperatures for Maxwellian [22]. MT= 16,17 Nuclear temperatures for Maxwellian [22] thresholds to 20 MeV. **************************************************************** REFERENCES 1. B.R. Leonard and K.B. Stewart, PNL (June 1967). 2. D.T. Goldman, Chart of the Nuclides, June 1964 3. H.H. Landon, Phys.Rev. 100, 1414 (1955) 4. J. Harvey, R. Block, Slaughter, report ORNL-59-2-83 (1959) 5. J. Harvey, D. Hughes, R. Carter, R. Pilcher, Phys.Rev. 99, 100 (1955) 6. M. Atoji, Phys.Rev. 121, 610 (1961) 7. J. Brunner and F. Widder, Nuclear Data for Reactors, Proc. Conf., Paris, France, October, 1966 (IAEA, 1967) p. 61 8. A.H. Baston, J.C. Lisle and G.S.G. Tuckey, J.Nucl.En. A13, 35 (1960) 9. H.W. Newson, Neutron Cross Section Technology, Proc. Conf., Washington, DC, March 1966 (AEC Tecnical Information Div., 1966) p. 562 10. J.M. Otter, report NAA-SR-11980, Vol.6 (1966) 11. D.G. Foster Jr. and D.W. Glasgow, Phys.Rev.C 3, 576 (1971) 12. E.H. Auerbach, report BNL-6562 (1962) 13. S. Pearlstein, Nucl.Sci.Eng. 23, 238 (1965) 14. R. Block et al., Neutron Time-of-Flight Methods, Proc. Conf. Saclay, France, July 1961 (EURATOM, 1961) p. 203 15. A.K. Chaubey and M.L. Sehgal, Nucl.Phys. 66, 267 (1965) 16. R.L. Macklin and J.H. Gibbons, Phys.Rev. 159, 1007 (1967) 17. B.T. Kenna and F.J. Conrad, report SC-RR-66-229 (1966) 18. R.F. Coleman et al., Proc.Phys.Soc. 73, 215 (1959) 19. G.M. Marcazzan, F. Tonolini and L. Zetta, Nucl.Phys. 46, 51 (1963) 20. R.F. Berland, report NAA-SR-11231 (1965) 21. Nucl.Data Sheets, 6-6-15 (June 1965) 22. S. Weinberg and E. Wigner, The Physical Theory of Nuclear Chain Reactions (U. of Chicago Press, 1958) 23. R.L. Macklin, D.M. Drake and J.J. Malanify, Los Alamos report LA-7479-MS (1978); data taken from EXFOR 10720.005. 24. S.F. Mughabghab, Neutron Cross Sections, Vol. 1, Neutron Resonance Parameters and Thermal Cross Sections (Academic Press, 1984)Back |