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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
J. Darvas, U. Hansen, E. Teuchert
Nuclear Technology | Volume 8 | Number 6 | June 1970 | Pages 496-506
Fuel | doi.org/10.13182/NT70-A28649
Articles are hosted by Taylor and Francis Online.
The use of Pu as a makeup fuel in D2O-moderated thorium converters is investigated. The reactor starts with plutonium, the bred 233U is reprocessed and fed back into the system. During reactor life there is a considerable change in fissile composition. The physics calculations follow the reactor through the whole running in period from the first core into a quasi-equilibrium state. For this type of system, the running in period makes an important contribution to the overall merits of the reactor. The physics of the Pu burner is compared in detail to a similar reactor using 235U as makeup fuel. The evaluation of fuel-cycle costs is performed with present worth methods, calculating quasi-equilibrium costs and average fuel-cycle costs for the reactor lifetime, running in period included. Thorium systems, starting and running with plutonium makeup, have to pay rather high penalties for the first refueling periods. The Pu value is estimated to be in the range of $9/g fissile.