کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
271383 | 504994 | 2013 | 7 صفحه PDF | دانلود رایگان |
• A new depletion code, FATI, has been developed for fusion applications.
• The code has been benchmarked against another well tested/benchmarked code, VESTA.
• The FATI code incorporates fusion specific features which are not present in current fission oriented depletion codes such as MONTEBURNS and VESTA.
Knowledge of nuclide burn-up within lithium blankets has a crucial part to play in the safety, reliability and feasibility of a fusion reactor. A new depletion interface code is presented called FATI (Fusion Activation and Transport Interface) which interfaces MCNP with FISPACT. The intended primary application of FATI is the simulation of nuclide burn-up within fusion reactor blankets. This paper describes some of the functionality of FATI and presents a comparison of percentage variation of the nuclide atomic densities, for a simple spherical blanket model, calculated by FATI and VESTA. The inventories of the two depletion interface codes differ by less than 1% for lithium and lead isotopes, while H and He isotopes differ by larger amounts due to variations in the methods used to model gas production in FISPACT and the PHOENIX burn-up codes.
Journal: Fusion Engineering and Design - Volume 88, Issue 11, November 2013, Pages 2891–2897