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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.
A. Ying, N. Morley, K. Gulec, B. Nelson, M. Youssef, M. Abdou
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 855-862
Fusion Blanket and Shield Technology (Poster Session) | doi.org/10.13182/FST98-A11963719
Articles are hosted by Taylor and Francis Online.
The attractive features and scientific challenges offered by the liquid wall systems render them strong candidates for investigation in the APEX project[1]. In particular, their high power density capabilities make the fusion reactors economically competitive. In this paper, as part of evolving a practical design based on this evolutionary idea, issues concerning thermalhydraulics of liquid surface first wall/blankets were analyzed. Design approaches as presently envisioned include both liquid films over the solid surface and gravity driven thick liquid jets using lithium and flibe as working fluids. The analyses involved defining liquid systems operating conditions, such as velocity and inlet/outlet temperatures, as well as to calculate free surface temperature so that the evaporation rate from the free surface would not jeopardize plasma operation while maintaining the liquid temperature within the operating windows for high thermal efficiencies. All analyses were performed for a neutron wall load of 10 MW/m2 and its corresponding surface heat flux of 2 MW/m2. The results indicated that high velocities, hard x-ray spectra and turbulent heat transfer enhancement were necessary conditions for keeping flibe first wall temperature low. On the other hand, at velocities of 20 m/s or higher, it appears possible to maintain lithium film evaporation rate below 1020#/m2s in an ARIES-RS type configuration. Nevertheless, present analyses have not uncovered any basic flaws or major shortcomings in the underlying scientific or technical arguments for the concepts. Yet, engineering innovations of how to maintain and control the flow and the associated analyses are still needed.