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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
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
Alecsei Sorokin
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 330-346
Technical Paper | doi.org/10.13182/NSE79-A20389
Articles are hosted by Taylor and Francis Online.
Chemically reactive nitrogen tetroxide (N2O4 ⇌ 2NO2 ⇌ 2NO + O2) is discussed as a possible working fluid for power-producing thermodynamic cycles. Computation of the thermodynamic properties of the dissociating N2O4 system in liquid and gas phases is based on Soviet sources, since the most extensive research has been carried on at the Institute for Nuclear Energy in Byelorussia, where N2O4 is proposed as a coolant for fast-neutron gas reactors. Kinetics of the chemical reactions are considered by comparison between cycle parameters with equilibrium working fluid in all plant components and computations with frozen second reaction in the turbines. The results of the research, and the pros and cons of the system from the thermodynamic point of view, are discussed in the conclusion.