The Nuclear Data and Measurement Series presents results of studies in the field of microscopic nuclear data. The primary objective is the dissemination of information in the comprehensive form required for nuclear technology applications. This Series is devoted to: a) measured microscopic nuclear parameters, b) experimental techniques and facilities employed in measurements, c) the analysis, correlation and interpretation of nuclear data, and d) the evaluation of nuclear data. Contributions to this Series are reviewed to assure technical competence and, unless otherwise stated, the contents can be formally referenced. This Series does not supplant formal journal publication, but it does provide the more extensive information required for technological applications (e.g. , tabulated numerical data) in a timely manner.
AbstractThe simultaneous evaluation of the cross sections of 6Li(n,a), 6Li(n,n), 1°B(n, a,), l0B(n, a,), '%(n,n), '97Au(n,y), 238U(n,y), 235U(n,f), 23%(n,f), and 238U(n,f) and the thermal constants was part of the evaluation of these data for ENDFB-VI. The FORTRAN codes and the data files used for the simultaneous evaluation are documented in the present report. Corrections for some data reported in the literature and the addition of several new data sets results in negligible changes except for the fission cross sections where minor changes occur relative to the evaluation for ENDFB-VI.
