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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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February 2025
Latest News
RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
Alex Galperin, Yigal Ronen
Nuclear Technology | Volume 58 | Number 3 | September 1982 | Pages 388-396
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32974
Articles are hosted by Taylor and Francis Online.
Received November 3, 1981 Accepted for Publication March 22, 1982 A symbiotic system of Pu-Th- and 233U-U-fueled reactors has been proposed and analyzed. The Pu-Th reactors utilize a tight lattice core and the 233U-U reactors utilize a regular pressurized water reactor (PWR) core. The two cases were investigated with different Pu-Th cores (system A: VM/VF =0.4 and system B: VM/VF - 1.0) and similar 233U-U cores. The cumulative 30-yr requirements of uranium ore and separative work for both systems were evaluated and indicated significant savings compared to current PWRs with plutonium recycle and the cross-progeny fuel cycle. The fuel cycle costs calculated for the proposed systems were slightly higher than those for the current PWR cycle.
