Output details
15 - General Engineering
University of Cambridge
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Output 0 of 0 in the submission
Article title
Efficient generation of one-group cross sections for coupled Monte Carlo depletion calculations
Type
D - Journal article
DOI
-
Title of journal
Nuclear Science and Engineering
Article number
-
Volume number
159
Issue number
1
First page of article
37
ISSN of journal
0029-5639
Year of publication
2008
URL
-
Number of additional authors
2
Additional information
The BGCore code system was developed based on an original method contained in this paper. It resolved non-negligible and systematic errors associated with the use of the fine-group spectrum tally method used in coupled Monte Carlo neutron transport - burnup codes. It is now widely used for modelling advanced reactors in teaching and research in such institutions as MIT (Prof Driscoll, ID_in_audit_file@mit.edu), Politecnico di Milano (Prof Marco Ricotti, ID_in_audit_file@polimi.it) and HZDR in Germany (Dr Soeren Kliem, ID_in_audit_file@hzdr.de).
Interdisciplinary
-
Cross-referral requested
-
Research group
None
Proposed double-weighted
No
Double-weighted statement
-
Reserve for a double-weighted output
No
Non-English
No
English abstract
-
