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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.”
P. F. Nichols, J. R. Worden, F. C. Engesser, R. E. Heineman
Nuclear Science and Engineering | Volume 15 | Number 3 | March 1963 | Pages 233-244
Technical Paper | doi.org/10.13182/NSE63-A26434
Articles are hosted by Taylor and Francis Online.
A series of experimental measurements has been made on the Experimental Gas Cooled Reactor (EGCR) lattice in the Physical Constants Test Reactor (PCTR). The measurements provide a broad basis for normalization of reactor calculations for lattices of this type. The fuel assembly is a cluster of seven uranium oxide rods, enriched in the U235 isotope and clad with stainless steel. The fuel is spaced on an eight-inch square pitch in a graphite moderator. Values of the lattice parameters k∝ , f, p, and e have been obtained for 1.8% enrichment of the uranium oxide fuel. The values of k∝ and f have also been obtained for 2.6% enrichment fuel. The techniques of using the PCTR have been extended so that supercell measurements may be made. The values of the strength of a boron carbide control rod and a stainless steel loop tube have been obtained in this way. The strength of such an inhomogeneous poison in the lattice is expressed as the difference in the supercell multiplication factor k∝ with and without the poison in the supercell. This difference is the same quantity which is obtained in the usual reactor cell calculation. The fuel temperature coefficient of for this cluster has also been measured between 50 and 500°C. The coefficient obtained is temperature dependent. The more important of the lattice parameters for the 1.8% enriched fuel are = 1.146 ± 0.004,f = 0.809 ± 0.005, p28 = 0.824 ± 0.006, ∈ = 1.019 ± 0.002, Δk (control rod -16 cell supercell) = -0.157 ± 0.012, Δk (empty loop tube -9 cell supercell) = -0.117 ± 0.011, and (l/k∞)(dk∞/dT) = -(0.68 ± 0.05) X 10-3T-1/2(oK)-1 For the 2.6% enriched fuel, results are k∞ = 1.256 ± 0.009 and f = 0.845 ± 0.006.