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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
WIPP’s SSCVS: A breath of fresh air
This spring, the Department of Energy’s Office of Environmental Management announced that it had achieved a major milestone by completing commissioning of the Safety Significant Confinement Ventilation System (SSCVS) facility—a new, state-of-the-art, large-scale ventilation system at the Waste Isolation Pilot Plant, the DOE’s geologic repository for defense-related transuranic (TRU) waste in New Mexico.
R. Schulten
Nuclear Science and Engineering | Volume 90 | Number 4 | August 1985 | Pages 388-390
Technical Paper | doi.org/10.13182/NSE85-A18486
Articles are hosted by Taylor and Francis Online.
For some time small high-temperature reactors, because of their special safety properties, have been of interest to various countries. The prototype of these facilities is the Arbeitsgemeinschaft Versuchsreaktor in Jülich. During the past 17 years of operation, the components of the reactor, especially the fuel elements, have proved suitable for achieving permanent temperatures of the heat transfer medium of up to 950 °C with low contamination of the loop. The convincing safety behavior of the reactor has been demonstrated. It is apparent that for this design an after heat removal system is not required, since the afterheat can be adequately removed by heat conduction. In addition to the thorium/uranium fuel cycle originally planned, utilization of low-enrichment uranium in the fuel elements has also been fully developed.