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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
J. V. Massey, A. Schneider
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 55-71
Technical Paper | Fuel Cycle | doi.org/10.13182/NT82-A32880
Articles are hosted by Taylor and Francis Online.
The use of a 238Pu “heat spike” has been proposed to render reactor-grade plutonium unattractive as a weapons material The technical feasibility of nuclear fuel cycles with plutonium containing 5 to 8% 238Pu was studied by investigating the production of 238Pu and its precursors (236U, 237Np, 241Am, and 242Cm) in light water reactors (LWRs) and in liquid-metal fast breeder reactors (LMFBRs). The effects of 238Pu and its precursors on reactor core behavior and fuel cycle operations were also analyzed. Modified LWR fuel management schemes allow the 238Pu content to build up to 5% in three reactor-fuel cycles and sufficient excess neptunium is generated for the concept to be expanded to all reactors in the fuel cycle in a timely manner. The production of 238Pu in LMFBRs is not self-sufficient. Tandem LWR-LMFBR fuel cycles (four LWRs to one LMFBR) are required to maintain a sufficient 238Pu level and a neptunium balance. The concept required small, but significant, increases in the initial fissile content of LWR fuel. Other LWR and all LMFBR core physics and reactivity parameters were not adversely affected. Required modifications to fuel cycle industries are within the present state of technology. An economic evaluation showed heat-spiked fuel cycles to be more costly than normal recycle fuel cycles (∼10 to 15% for LWRs and ∼30% for LMFBRs), but to be 10 to 15% less expensive than the LWR throwaway fuel cycle. In summary, the heat spike concept was found to be technically and economically feasible, but its adoption for LMFBRs might retard breeder introduction and growth schedules.