کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
295999 511699 2016 12 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Development of modern CANDU PHWR cross-section libraries for SCALE
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Development of modern CANDU PHWR cross-section libraries for SCALE
چکیده انگلیسی


• New ORIGEN libraries for CANDU 28 and 37-element fuel assemblies have been created.
• These new reactor data libraries are based on modern ENDF/B-VII.0 cross-section data.
• The updated CANDU data libraries show good agreement with radiochemical assay data.
• Eu-154 overestimated when using ENDF-VII.0 due to a lower thermal capture cross-section.

A new set of SCALE fuel lattice models have been developed for the 28-element and 37-element CANDU fuel assembly designs using modern cross-section data from ENDF-B/VII.0 in order to produce new reactor data libraries for SCALE/ORIGEN depletion analyses. These new libraries are intended to provide users with a convenient means of evaluating depletion of CANDU fuel assemblies using ORIGEN through pre-generated cross sections based on SCALE lattice physics calculations. The performance of the new CANDU ORIGEN libraries in depletion analysis benchmarks to radiochemical assay data were compared to the previous version of the CANDU libraries provided with SCALE (based on WIMS-AECL models).Benchmark comparisons with available radiochemical assay data indicate that the new cross-section libraries perform well at matching major actinide species (U/Pu), which are generally within 1–4% of experimental values. The library also showed similar or better results over the WIMS-AECL library regarding fission product species and minor actinoids (Np, Am, and Cm). However, a notable exception was in calculated inventories of 154Eu and 155Eu, where the new library employing modern nuclear data (ENDF/B-VII.0) performed substantially poorer than the previous WIMS-AECL library (which used ENDF-B/VI.8 cross-sections for these species). The cause for this discrepancy appears to be due to differences in the 154Eu thermal capture cross-section between ENDF/B-VI.8 and ENDF/B-VII.0, an effect which is exacerbated by the highly thermalized flux of a CANDU heavy water reactor compared to that of a typical light-water reactor spectrum.Overall, the new SCALE-based CANDU libraries appear to give very good agreement to experimental benchmarks, indicating that the new libraries should provide satisfactory depletion calculation performance generally comparable or better to the prior WIMS-AECL libraries.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 302, Part A, June 2016, Pages 56–67
نویسندگان
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