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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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.
Kazuo Hiramoto, Motoo Aoyama, Masaharu Sakagami, Renzo Takeda
Nuclear Technology | Volume 64 | Number 3 | March 1984 | Pages 243-248
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT84-A33354
Articles are hosted by Taylor and Francis Online.
Low density UO2 fuel pellets of an annular type are used to solve two problems related to high-discharge burnup: the enhancement of the pellet /cladding mechanical interaction, which increases cladding permanent strain, and the increase in average neutron energy due to high enrichment, which changes the core neutronic characteristics. As an example, the design concept is applied to boiling water reactor fuel rods having 57 effective full-power months (EFPMs). The fuel pellet density and the center hole diameter are determined to be 90% TD and 3.0 mm, respectively. The cladding permanent strain of the proposed fuel rod at EFPMs of 57 can be kept lower than the current fuel rod at 36 EFPMs. The EFPMs of 36 and 5 7 correspond respectively to the average discharge burnups of ∼30 and 50 GWd/ tonne U. With an enrichment of 4.5 wt%, the former rods provide the same neutronic characteristics as that of current rods with 2.8 wt% enrichment. Furthermore, power generation cost in the newly designed core is reduced by ∼10% from present cost levels.