Abstract
A new nuclear data library for the CASMO5 advanced lattice physics code has been generated based on the recently-released ENDF/B-VIII.0 evaluation. The ENDF/B-VIII.0 evaluation represents the state-of-the-art in nuclear data and features new evaluations from the CIELO project for 1H, 16O, 56Fe, 235U, 238U and 239Pu. A description of the library generation procedure used to process these data into the CASMO5 586 energy group structure is provided. Initial validation of the new ENDF/B-VIII.0-based library, referred to as the E8R0 library, is also presented and involves the comparison of predicted k–eff and fission rate distributions to measurements from various critical experiments. The critical experiments used in the initial validation of the E8R0 library consist of the B&W 1810 series, B&W 1484 series, DIMPLE S06A/B, and TCA reflector experiment with iron plates. The results from the initial validation indicate that the new E8R0 library provides a satisfactory performance in terms of CASMO5 predicted k–eff and fission distributions.
Highlights
The fundamental nuclear data used in the generation of multi-group, incident-neutron cross sections is the starting point and foundation of all nuclear reactor simulation and analysis
The Core Management System 5 (CMS5) two-step scheme involves the use of the CASMO5 [1] advanced lattice physics code for the generation of homogenized data for downstream use by the SIMULATE5 [2] advanced three-dimensional nodal simulator, which supports the analysis of Boiling Water Reactors (BWRs), Pressurized Water Reactors (PWRs) [3] and VVERs [4,5]
The objectives of this work are to provide a description of the library generation procedure used to process the recently-released ENDF/B-VIII.0 [6] evaluation into a new commercially available CASMO5 586 energy-group library, referred to as the E8R0 library, and present the initial validation of the E8R0 library using several critical experiments
Summary
The fundamental nuclear data used in the generation of multi-group, incident-neutron cross sections is the starting point and foundation of all nuclear reactor simulation and analysis. The objectives of this work are to provide a description of the library generation procedure used to process the recently-released ENDF/B-VIII.0 [6] evaluation into a new commercially available CASMO5 586 energy-group library, referred to as the E8R0 library, and present the initial validation of the E8R0 library using several critical experiments. The ENDF/B-VIII.0 nuclear data evaluation was released by the Cross Section Evaluation Working Group (CSEWG) on February 2, 2018. All major nuclides present in current-generation LWR fuel, coolant, absorber and structural materials possess new evaluations in the ENDF/B-VIII.0 release. This new evaluation may impact the prediction of core parameters such as k–eff, temperature coefficients, cycle length, reflector savings, activation and spent fuel characterization. The TALYS-based Evaluated Nuclear Data Library 2017 (TENDL-2017) [8,9] is used to supplement the ENDF/B-VIII.0 evaluation
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