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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.
S. C. Cohen, R. A. Moore, J. C. Young, J. L. Russell, Jr.
Nuclear Science and Engineering | Volume 37 | Number 1 | July 1969 | Pages 111-126
Technical Paper | doi.org/10.13182/NSE69-A20903
Articles are hosted by Taylor and Francis Online.
The neutron spectrum for a subcritical section of the thermionic critical experiment, Assembly No. 1, was measured by the pulsed source, time-of-flight method. The measurement was performed in a calculable slab configuration so that the results would be directly applicable to the critical assembly. The measured spectrum was compared with multigroup transport calculations based upon various cross-section data sets and cross-section treatments. The results demonstrate the need for consideration of unresolved resonance self-shielding in 235U, and suggest that the 235U absorption cross-section data may be slightly high at low energies (100 eV < E < 2 keV).