"PROCESS": a systems code for fusion power plants - Part 2:Engineering

TL;DR

PROCESS is a flexible systems code that evaluates the engineering and economic viability of fusion power plants, incorporating customizable constraints and new algorithms for safety, materials, and operational parameters.

Contribution

This paper introduces detailed engineering algorithms for the PROCESS code, enabling comprehensive assessment of fusion plant design constraints and operational limits.

Findings

Assessment of thermal efficiency based on coolant temperature

Estimation of capacity factor considering downtime and pulsed operation

Implementation of stress limits in toroidal field coil design

Abstract

PROCESS is a reactor systems code - it assesses the engineering and economic viability of a hypothetical fusion power station using simple models of all parts of a reactor system. PROCESS allows the user to choose which constraints to impose and which to ignore, so when evaluating the results it is vital to study the list of constraints used. New algorithms submitted by collaborators can be incorporated - for example safety, first wall erosion, and fatigue life will be crucial and are not yet taken into account. This paper describes algorithms relating to the engineering aspects of the plant. The toroidal field (TF) coils and the central solenoid are assumed by default to be wound from niobium-tin superconductor with the same properties as the ITER conductors. The winding temperature and induced voltage during a quench provide a limit on the current density in the TF coils. Upper limits are placed on the stresses in the structural materials of the TF coil, using a simple two-layer model of the inboard leg of the coil. The thermal efficiency of the plant can be estimated using the maximum coolant temperature, and the capacity factor is derived from estimates of the planned and unplanned downtime, and the duty cycle if the reactor is pulsed. An example of a pulsed power plant is given.