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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
H. Makowitz
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 136-143
Technical Paper | doi.org/10.13182/NSE86-A17874
Articles are hosted by Taylor and Francis Online.
Numerical experiments performed on a single instruction multiple data-pipeline vector parallel (SIMD-PVP) architecture computing machine, e.g., a CRAY X-MP/48, demonstrate that current nuclear reactor systems codes can be restructured for concurrent multiprocessing and show wall clock performance improvements of 1.5 to 3.0 on a 4-CPU machine, depending on plant model, problem type, and problem length. In addition, algorithm development studies indicate that up to a 20% speedup can be obtained by a new class of parallel numerical methods. Faster-than-real-time simulation has been demonstrated utilizing RELAP5/MOD1 and a pressurized water reactor plant model characteristic of licensing and/or safety analysis calculations. A theoretical analysis indicates that five to ten times faster than real-time computation may be possible for this class of problems utilizing this or the next generation of SIMD-PVP architecture machines, such as the CRAY X-MP/48, and new computer codes optimized for such machines.