The development of a fusion specific depletion interface code-FATI

作者：Morgan L W G^*; Packer L W; Haeck W; Pasley J

来源：Fusion Engineering and Design, 2013, 88(11): 2891-2897.

DOI：10.1016/j.fusengdes.2013.05.105

• Tritium breeding
• Neutronics
• Fusion
• Depletion

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 FAT! (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.

• 出版日期2013-11