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WIPP: Lessons in transportation safety
As part of a future consent-based approach by the federal government to site new deep geologic repositories for nuclear waste, local communities and states that are considering hosting such facilities are sure to have many questions. Currently, the Waste Isolation Pilot Plant in New Mexico is the only example of such a repository in operation, and it offers the opportunity for state and local officials to visit and judge for themselves the risks and benefits of hosting a similar facility. But its history can also provide lessons for these officials, particularly the political process leading up to the opening of WIPP, the safety of WIPP operations and transportation of waste from generator facilities to the site, and the economic impacts the project has had on the local area of Carlsbad, as well as the rest of the state of New Mexico.
Farrokh Najmabadi
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1286-1292
Power Plant Design and Technology | doi.org/10.13182/FST96-A11963125
Articles are hosted by Taylor and Francis Online.
The Starlite Project was initiated to investigate the mission, requirements and goals, features, and the R&D needs of the Fusion Demonstration Power Plant based on tokamak confinement concept. It is obvious that the Fusion Demo should demonstrate that a commercial fusion power plant would be accepted by utility and industry (i.e., it is affordable and profitable) and by the general public and government (i.e., it has superior safety and environmental features). Therefore, as the first step in the Starlite project, a set of quantifiable top-level requirements, and goals for both commercial fusion power plants and the Fusion Demo were developed. Next, several candidate options for physics operation regime as well engineering design of various components (e.g., choice of structural material, coolant, breeder) have been developed and assessed. In each area, this assessment was aimed at investigating (1) the potential to satisfy the requirements and goals, and (2) the feasibility e.g., critical issues and credibility (e.g., degree extrapolation required from present data base). This assessment led to the choice of the reversed-shear as the tokamak plasma operation regime and a self-cooled lithium design with vanadium alloy for blanket and in-vessel structures for detailed design. This paper presents a summary of top-level requirements and goals for fusion power and overviews the results of our assessment of tokamak plasma physics and technology options and designs.