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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
December 2024
Nuclear Technology
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November 2024
Latest News
Bipartisan Nuclear REFUEL Act introduced in the U.S. House
To streamline the licensing requirements for nuclear fuel recycling facilities and help increase investment in nuclear energy in the United States, U.S. Reps. Bob Latta (R., Ohio) and Scott Peters (D., Calif.) have introduced the bipartisan Nuclear REFUEL Act in the House of Representatives.
The bill, introduced on December 6, would amend the definition of “production facility” in the Atomic Energy Act, clarifying that a reprocessing facility producing uranium-transuranic mixed fuel would be licensed only under 10 CFR Part 70. According to the lawmakers, this single-step licensing process would significantly streamline the licensing requirements for fuel recycling facilities.
Jun-Yun Yang, Xiao Gang, Yang-Jun Ying
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 538-554
Technical Paper | doi.org/10.13182/NSE15-44
Articles are hosted by Taylor and Francis Online.
A code called CriSAA used for criticality excursion evaluation and analysis is developed by coupling a two-dimensional thermal-hydraulic code and a zero-dimensional neutron kinetics code. The generalized semi-Markov process simulation method is improved in the neutron kinetics code, which makes it suitable for the transient cases of both stochastic and intense neutron fields. Pulse withdrawal experiments and ramp feed experiments performed on the Transient Experiment Critical Facility (TRACY) are simulated with CriSAA. The transient characteristics of isolated and open criticality excursions on TRACY are studied. The simulation fits well with the experiments. Stochastic phenomena of the criticality excursions under a weak source case are studied. The statistics characteristics, including time and energy to first peak, power of first peak, and total energy, are shown. This work provides an advanced approach for criticality excursion evaluation and analysis.
