ACTYS-ASG, tool for coupling ACTYS-1-GO with ATTILA

摘要

As part of ACTYS project, two state of the art nuclear activation codes are developed. The first code ACTYS calculates nuclear activation for single material and a single neutron spectrum. The second code ACTYS-1-GO, is based on a faster and accurate algorithm for activation calculations at multiple locations with different neutron flux spectrum and different material composition. It can be used for a faster and accurate estimation of nuclear response in a typical fusion machine. In order to estimate biological dose rates due to delayed gammas from neutron irradiated materials, codes like ACTYS-1-GO should be coupled with transport codes like MCNP or ATTILA. The present paper discusses the coupling of ACTYS-1-GO with transport code ATTILA. The coupling has been achieved by using ACTYS-1-GO as an activation source generator (ASG) for subsequent gamma transport in ATTILA. The mathematical and algorithmic details of the coupling are explained in the paper. The details of sharing the geometric and other information between the two codes along with validation procedure are also discussed. Further, the importance of highly resolved calculations over a coarse calculation for fusion systems is also included. The main advantage of coupling presented in this work is to achieve such better resolved calculations without sacrificing the computational performance.