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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Hatice Akkurt, Naeem M. Abdurrahman
Nuclear Technology | Volume 127 | Number 3 | September 1999 | Pages 301-314
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A3003
Articles are hosted by Taylor and Francis Online.
In 1967, a series of critical experiments were conducted at the Westinghouse Reactor Evaluation Center under the joint sponsorship of the Empire State Atomic Development Associates (ESADA) and Westinghouse using mixed-oxide (MOX) fuel. During the experimental program, both single- and multiregion critical core configurations were constructed for different fuel types and lattice pitches. Two types of MOX fuels and a low-enriched UO2 fuel were used. A description of selected single-region ESADA experiments with criticality benchmark calculation results for those experiments as well as sensitivity analysis results on some configurations is given. Criticality calculations were performed using MCNP-4A with both ENDF/B-V and ENDF-B/VI cross-section libraries. The calculational results show that the calculated eigenvalues with ENDF/B-V cross-section libraries are higher than calculated eigenvalues with ENDF/B-VI cross-section libraries for all types of fuel. Calculational results also indicate that there is an increase in keff with increasing lattice pitch with both cross-section libraries. The uncertainties in keff value due to some uncertainties in the measured data are also calculated.