Benchmarking FENDL-2.1 with impact of ENDF/B-VII.0 release on nuclear heating and damage

Author

Sawan, M.E.

Author_Institution

Fusion Technol. Inst., Univ. of Wisconsin-Madison, Madison, WI, USA

fYear

2009

fDate

1-5 June 2009

Firstpage

1

Lastpage

4

Abstract

MCNP calculations for a calculational benchmark representative of an early ITER design were carried out to investigate the impact of ENDF/B-VII.0 release on FENDL-2.1. The results presented in this work clearly show that the previously observed differences in nuclear heating and radiation damage are removed when the correctly processed ENDF/BVII. 0 data are used. Differences in all nuclear parameters are very small (< 1%) implying that minimal impact is expected on ITER analysis and updating the FENDL-2.1 library is not urgently needed for ITER analysis. Calculations for an inertial fusion power plant showed larger changes in nuclear heating, and radiation damage due to the large changes in the H-3 and Au-197 data that affect the energy spectrum of neutrons emitted from the ICF target. The results confirm the need for updating FENDL-2.1 for use in analysis of fusion systems beyond ITER.

Keywords

Tokamak devices; fusion reactor design; fusion reactor targets; fusion reactor theory; radiation effects; ENDF-B-VII.0 data; FENDL-2.1library; ICF target; ITER calculational benchmark; ITER design; MCNP calculations; energy spectrum; fusion evaluated nuclear data library; inertial fusion power plant; nuclear heating; nuclear parameters; radiation damage; Atomic measurements; Chemical elements; Geometry; Heating; Isotopes; Libraries; Neutrons; Plasma sources; Power generation; Uncertainty; ITER; nuclear data; nuclear heating; radiation damage;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on

Conference_Location

San Diego, CA

Print_ISBN

978-1-4244-2635-5

Electronic_ISBN

978-1-4244-2636-2

Type

conf

DOI

10.1109/FUSION.2009.5226370

Filename

5226370