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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Danhua ShangGuan, Gang Li, Baoyin Zhang, Li Deng, Yan Ma, Yuanguan Fu, Rui Li,Xiaoli Hu
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 555-562
Technical Paper | doi.org/10.13182/NSE15-32
Articles are hosted by Taylor and Francis Online.
Based on the inspiration of the uniform fission site (UFS) algorithm, we propose a strategy for biasing fission secondary neutrons using tally density obtained from past cycles in a Monte Carlo criticality calculation when the purpose is to seek high-performance global tallying. Using this strategy for global volume-averaged cell flux and energy deposition tallies when performing criticality calculations on a pin-by-pin model of the Dayawan nuclear power station nuclear reactor yields better performance. All the strategies (including the original UFS algorithm) are implemented in a parallel Monte Carlo particle transport code JMCT (J Monte Carlo Transport), which is recently developed software constructed on the framework of JCOGIN (J COmbinatorial Geometry Monte Carlo transport INfrastructure).