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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Digital control system installed at China’s Linglong One
Earlier this month, the first digital control system was put in place at Linglong One, a small modular reactor demonstration project being built at the Changjiang nuclear power plant in Hainan Province. This is the world’s first land-based commercial SMR and is controlled by China National Nuclear Power Co. Ltd., a subsidiary of the China National Nuclear Corporation (CNNC).
C. Parisi, E. Negrenti, M. Pecchia
Nuclear Science and Engineering | Volume 178 | Number 4 | December 2014 | Pages 524-538
Technical Paper | doi.org/10.13182/NSE14-40
Articles are hosted by Taylor and Francis Online.
This paper summarizes the evaluation for core I and core VIII of the Babcock & Wilcox Spectral Shift Control Reactor critical experiment program. The Spectral Shift Control Reactor concept, moderated and cooled by a variable mixture of heavy and light water, envisaged changing of the thermal neutron spectrum during the operation to encourage breeding and to sustain the core criticality. Core I contained 484 fuel rods with 4% UO2 fuel in light water while core VIII contained 2188 fuel rods with 93% enriched UO2-ThO2 fuel in a moderator mixture of heavy and light water. For core I, the criticality experiment and measurements of the thermal disadvantage factor were evaluated. For core VIII, only the criticality experiment was evaluated. For both cores, experimental uncertainties were determined confirming the good level of accuracy achieved by the experimentalists. Based on the experimental configurations, benchmarks were proposed, and their biases were determined.