Tokamaks are often considered to be a leading candidate for near-term, cost-effective fusion energy, but these devices are susceptible to sudden loss of confinement events called disruptions. The threat of disruptions has garnered serious attention in research for the next generation of burning plasma experiments, such as ITER, but has received little treatment in economic studies of magnetic fusion energy. In this paper, we present a model for quantifying the effect of disruptions on the cost of electricity produced by a tokamak power plant (TPP). We outline the various ways disruptions increase costs and decrease revenues, introduce metrics to quantify these effects, and add them to a levelized cost of electricity (LCOE) model. Additionally, we identify several rate-limiting repair steps and introduce a classification system of disruption types based on the time to return to operations. We demonstrate how the LCOE model can be used to find the cost of electricity and the requirements for disruption handling of a TPP, and we further highlight where future research can have a strong impact in neutralizing the "showstopping" potential of disruptions.

This grant supported two primary activities at the MIT Plasma Science and Fusion Center. First, personnel support, hardware upgrades, and software development were used to maintain the C-Mod data archive set. This highly valuable repository contains all of the data generated from operation of the Alcator C-Mod FES User Facility, covering first operation in 1992 through completion of the final experimental campaign on Sept 30, 2016. The archive, stored using the MDSplus architecture, also includes all of the data analysis, which is ongoing, and most of the results of computer modeling of the data. Second, this grant supported activities related to participation of the C-Mod team in the International Tokamak Physics Activites (ITPA), which includes analysis of C-Mod data, in conjunction with data from tokamaks operated around the world, with intense coordination of joint experiments.

In October 2003, Dr. Raymond Orbach, Director of the Department of Energy’s Office of Science, issued a charge to the Fusion Energy Sciences Advisory Committee (FESAC) “to identify the major science and technology issues that need to be addressed, recommend how to organize campaigns to address these issues, and recommend the priority order for these campaigns.” The sections in this report document the results of the Panel’s work. The first two sections describe the concepts of the overarching themes, topical scientific questions, and campaigns. The next six sections (Sections 3–8) describe in detail the six scientific campaigns. Section 9 describes some important enabling research activities necessary for the campaigns. Sections 10–12 describe the overarching themes, which provide a crosscutting perspective of the activities in the six campaigns. Finally, the Panel’s recommendations are set forth in Section 13. The charge letter to the panel is provided as Appendix A; the FESAC response letter is provided as Appendix D.

This panel was set up by the U.S. Department of Energy's Fusion Energy Sciences Advisory Committee in response to a request from the department to prepare a strategy for the study of burning fusion plasmas. Experimental study of a burning plasma has long been a goal of the U.S. science-based fusion energy program. There is an overwhelming consensus among fusion scientists that we are now ready scientifically, and have the full technical capability, to embark on this step. The fusion community is prepared to construct a facility that will allow us to produce this new plasma state in the laboratory, uncover the new physics associated with the fusion burn, and develop and test new technology essential for fusion power. Given this background, the panel has produced a strategy to enable the United States to proceed with this crucial next step in fusion energy science. The strategy was constructed with awareness that the burning plasma program is only one major component in a comprehensive development plan for fusion energy. A strong core science and technology program focused on fundamental understanding, confinement configuration optimization, and the development of plasma and fusion technologies essential to the realization of fusion energy. The core program will also be essential to the successful guidance and exploitation of the burning plasma program, providing the necessary knowledge base and scientific workforce.

This report presents the results and recommendations of the U. S. Department of Energy Fusion Energy Advisory Committee (FEAC) review of its Inertial Fusion Energy (IFE) program. The subpanel charged with the review was chaired by John Sheffield of Oak Ridge National Laboratory. The FEAC, to which the subpanel reported, was chaired by Robert Conn of the University of California at San Diego.

Alcator C-Mod is a high field, compact tokamak facility, which commenced operation in the fall of 1991. The device incorporates strong shaping and magnetic divertor capability, with high-power ICRF auxiliary heating and pellet fueling. Diagnosing the plasma properties of Alcator C-Mod poses numerous challenges. Detailed profile information will be required in order to understand the transport and confinement properties of the various regimes which will be explored. Diagnostic techniques which will be employed include laser scattering, interferometry, reflectometry, photon and particle spectroscopy, bolometry, and electric and magnetic probes. Parameters which will be measured include temperatures and densities (two-dimensional profiles in the confinement region), radiated power, Zeff , current density, fusion reactivity, MHD activity, and flux surface shape. Specific experiments to measure density and temperature fluctuations are also planned. Special emphasis has been placed on measurements of the properties of the edge plasma, with facilities to measure fueling and recycling fluxes, edge temperatures and densities (including neutrals), power flows, and impurity sources and transport in the limiter and divertor regions. This work is supported by U.S. Department of Energy Contract No. DE-AC02-78ET51013.