Compared performances of ENDF/B-VI and JEF-2.2 for MOX core physics
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:298337
- Argonne National Lab., IL (United States)
The United States is currently evaluating the use of mixed-oxide (MOX) fuel in commercial light water reactors for reducing weapons-grade Pu stockpiles. The design and licensing processes will require that the validity of the nuclear data libraries and codes used in the effort be demonstrated. Unfortunately, there are only a very limited number of relatively old and nonrepresentative integral experiments freely available to the US programs. This lack of adequate experimental data can be partially remediated by comparing the results of well-validated European codes with the results of candidate US codes. The authors have compared the performances of the JEF-2.2 and ENDF/B-VI.4 libraries for a series of benchmarks for k{sub eff}, void worth, and pin power distributions. Note that JEF-2.2 has been extensively validated for MOX applications. To obtain systematic comparisons between JEF-2.2 and ENDF/B-VI results, the two libraries were implemented with the same processing code options in two independent code systems: (1) VIM, a continuous-energy Monte Carlo code developed at Argonne National Laboratory, with its own processing codes independent of NJOY; and (2) DRAGON, a two-dimensional lattice code developed at Ecole Polytechnique de Montreal. A standard 172-energy-group structure was used in the NJOY processing code.
- OSTI ID:
- 298337
- Report Number(s):
- CONF-981106--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 79; ISSN TANSAO; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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