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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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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.
Alireza Haghighat, Maurice A. Robkin
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 503-513
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33175
Articles are hosted by Taylor and Francis Online.
The long-term reduction in potential hazard of geologically stored nuclear wastes achievable by partitioning and transmutation (PT) of the actinides discharged from a mixed-oxide (MOX)-fueled light water reactor coupled to a MOX-fueled liquid-metal fast breeder reactor (LMFBR) is considered for three PT cases:1. 32 cycles of PT with plutonium sent to the repository at every cycle2 .same as item 1 with plutonium sent to the LMFBR as fuel3. PT cycles continued indefinitely.Cross-section and isotope inventory data are taken from the literature for similar facilities and processes and converted to an effective cycle-by-cycle burnup pattern. The effect of PT on potential population hazard into the indefinite future is evaluated on the basis of activity leached from the repository, transported by groundwater, and ingested. The calculation is carried out with two different sets of losses of actinides from facilities, one of which includes very small uranium and plutonium losses. The short-term fatalities expected due to accidents and operational releases are increased up to 67%. The decrease in long-term potential hazard with PT is minimal with the standard loss fractions. In the small loss set, the loss of uranium (which dominates the long-term hazard) is assumed to be very small. The factor of 25 reduction observed in this case is reduced to a factor of 3 when uranium is deleted from the tally. With uranium deleted, both loss fraction sets give the same long-term hazard reduction with PT.