DocumentCode :
1064954
Title :
JEFF-3.1, ENDF/B-VII and JENDL-3.3 Critical Assemblies Benchmarking With the Monte Carlo Code TRIPOLI
Author :
Suble, Jean-Christophe
Author_Institution :
Commissariat a l´´Energie Atomique, St. Paul lez Durance
Volume :
55
Issue :
1
fYear :
2008
Firstpage :
604
Lastpage :
613
Abstract :
ENDF/B-VII.0, the first release of the ENDF/B-VII nuclear data library, was formally released in December 2006. Prior to this event the European JEFF-3.1 nuclear data library was distributed in April 2005, while the Japanese JENDL-3.3 library has been available since 2002. The recent releases of these neutron transport libraries and special purpose files, the updates of the processing tools and the significant progress in computer power and potency, allow today far better leaner Monte Carlo code and pointwise library integration leading to enhanced benchmarking studies. A TRIPOLI-4.4 critical assembly suite has been set up as a collection of 86 benchmarks taken principally from the International Handbook of Evaluated Criticality Benchmarks Experiments (2006 Edition). It contains cases for a variety of U and Pu fuels and systems, ranging from fast to deep thermal solutions and assemblies. It covers cases with a variety of moderators, reflectors, absorbers, spectra and geometries. The results presented show that while the most recent library ENDF/B-VII.0, which benefited from the timely development of JENDL-3.3 and JEFF-3.1, produces better overall results, it suggest clearly also that improvements are still needed. This is true in particular in Light Water Reactor applications for thermal and epithermal plutonium data for all libraries and fast uranium data for JEFF-3.1 and JENDL-3.3. It is also true to state that other domains, in which Monte Carlo code are been used, such as astrophysics, fusion, high-energy or medical, radiation transport in general benefit notably from such enhanced libraries. It is particularly noticeable in term of the number of isotopes, materials available, the overall quality of the data and the much broader energy range for which evaluated (as opposed to modeled) data are available, spanning from meV to hundreds of MeV. In pointing out the impact of the different nuclear data at the library but also the isotopic levels one could not help no- ticing the importance and difference of the compensating effects that result from their single usage. Library differences are still important but tend to diminish due to the ever increasing and beneficial worldwide collaboration in the field of nuclear data measurement and evaluations.
Keywords :
Monte Carlo methods; fission reactor fuel; libraries; moderators; neutron transport theory; nuclear criticality safety; nuclear engineering computing; plutonium; uranium; ENDF-B-VII; International Handbook of Evaluated Criticality Benchmarks Experiments; JEFF-3.1; JENDL-3.3 library; Light Water Reactor; Monte Carlo code; TRIPOLI-4.4 critical safety; absorbers; benchmarking studies; epithermal plutonium; fuel assemblies; geometries; moderators; neutron transport libraries; nuclear data library; radiation transport; reflectors; uranium; Assembly systems; Astrophysics; Fuels; Geometry; Inductors; Isotopes; Lead; Libraries; Monte Carlo methods; Neutrons; Benchmarking; ENDF/B-VII; JEFF-3.1; JENDL-3.3; Monte Carlo; TRIPOLI-4.4;
fLanguage :
English
Journal_Title :
Nuclear Science, IEEE Transactions on
Publisher :
ieee
ISSN :
0018-9499
Type :
jour
DOI :
10.1109/TNS.2007.911600
Filename :
4448541
Link To Document :
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