Fusion Science and Technology / Volume 8 / Number 1P2A / July 1985 / Pages 995-1000
Shielding Neutronic / Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) / dx.doi.org/10.13182/FST85-A40163
Articles are hosted by Taylor and Francis Online.
As part of the GA-funded TFCX proposal effort, a method was developed and implemented to make fast, repetitive calculations of fusion reactor shutdown dose rates for several operating and shutdown times. The ONEDANT discrete ordinates code is used as the transport code in this procedure. Examples of parametric study results using this method are given. The method is currently being used in tokamak ignition studies at GA.