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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
H. G. Groehn
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 392-400
Heat Transfer and Fluid Flow | doi.org/10.13182/NT82-A32866
Articles are hosted by Taylor and Francis Online.
The effect of cross flow on the main coolant flow was studied at a two block test section on the model scale of 1:1. The cross flow was introduced through a wedge-shaped gap located between the two succeeding fuel blocks mentioned. The gap width varied from 1.85 to 6 mm. The entrance area for the cross flow was modified by the arrangement of blocking pieces around the circumference of the gap. The velocity distribution over the cross section of the fuel blocks and the pressure loss over the gap were measured. The experimental results allow the prediction of the flow reduction in each coolant channel of the fuel block depending on the transverse pressure gradient driving the cross flow.
