Development of modern CANDU PHWR cross-section libraries for SCALE
•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 du...
Gespeichert in:
Veröffentlicht in: | Nuclear engineering and design 2016-06, Vol.302 (PA), p.56-67 |
---|---|
Hauptverfasser: | , |
Format: | Artikel |
Sprache: | eng |
Schlagworte: | |
Online-Zugang: | Volltext |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
Zusammenfassung: | •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. |
---|---|
ISSN: | 0029-5493 1872-759X |
DOI: | 10.1016/j.nucengdes.2016.04.007 |