Abstract The Applied Radiation Physics Group at Culham Centre for Fusion Energy, United Kingdom, has developed and applied state-of-the-art radiation mapping methods and tools. The tools enable complex shielding calculations in and around fusion devices, both during and after plasma operations, to inform on associated radiation fields for operational, maintenance, and remote handling scenarios, for example. Here, we present a description and application of those tools to produce radiation maps to support (a) the Joint European Torus (JET) operational safety case for a new D-T campaign that is foreseen for 2020, with neutron emission rates in excess of 1018 n/s and a total neutron yield up to 1.7 × 1021 n, and (b) the ITER device. Three tools are presented in this paper: An automated global variance reduction tool applied to the JET facility; a portable bounding surface source referred to as a mesh source, which has been applied to activated materials; and a smeared source routine, which enables the calculation of integral fields associated with moving sources. These tools are demonstrated, in combination, to produce the integrated three-dimensional dose map of an activated divertor component being transported through a path within the ITER facility.
[1]
Edward W. Larsen,et al.
Automated Weight Windows for Global Monte Carlo Particle Transport Calculations
,
2001
.
[2]
A. Turner,et al.
Improving computational efficiency of Monte-Carlo simulations with variance reduction
,
2013
.
[3]
Andrew A. Davis,et al.
APPLICATION OF NOVEL GLOBAL VARIANCE REDUCTION METHODS TO FUSION RADIATION TRANSPORT PROBLEMS
,
2011
.
[4]
Clell J. Solomon,et al.
Statistical assessment of numerous Monte Carlo tallies
,
2011
.
[5]
Yican Wu,et al.
CAD-based interface programs for fusion neutron transport simulation
,
2009
.
[6]
P. Vaz.
Neutron transport simulation (selected topics)
,
2009
.