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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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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Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
Yuxuan Liu, Kyle Vaughn, Brendan Kochunas, Thomas Downar
Nuclear Science and Engineering | Volume 195 | Number 1 | January 2021 | Pages 50-68
Technical Paper | doi.org/10.1080/00295639.2020.1780853
Articles are hosted by Taylor and Francis Online.
Over the years, significant validation work for the neutronics code MPACT has been performed against zero-power critical benchmarks and measured data from operating nuclear power plants. Among all of these efforts, however, validation of the pin-resolved capability in MPACT has been limited by the public availability of experimental data and to a lesser degree availability of measurement techniques and facilities that provide such detailed data. Recently, new measurement results to experimentally determine the reaction rate along the pellet radius from the IPEN/MB-01 research reactor facility (IPEN) have been published as a benchmark in the International Reactor Physics Experiment Project handbook. In this paper, we examine MPACT simulation results for several IPEN benchmark experiments with emphasis on the intrapin reaction rate measurements. The IPEN critical experiments with variations in system temperature and gadolinium loadings are modeled first with the latest MPACT cross-section library and linear source (LS) method of characteristics (MOC) capability. The MPACT results of two-dimensional (2-D) models with axial buckling are within 160 pcm from the experimental eigenvalues using the flat source MOC. Using the LS MOC, the errors are no more than 70 pcm, and the temperature trend of various cases is smaller. The MPACT three-dimensional models with LS show slightly worse comparisons than the 2-D models, which may be due to the isotropic transverse leakage and homogenized cross-section approximations of the 2-D/one-dimensional solver. For the reaction rate validation, MPACT produces intrapin reaction rate results within 2σ of the experiment and shows excellent agreement with the Monte Carlo solution. The observed discrepancies between the simulated results and experiment for the fission rate measurements are discussed. The kinetics parameters measured in another IPEN experiment are also compared with MPACT simulations using different kinetics data sources. According to the validation results, JENDL-4.0 and Santamarina et al.’s data are recommended for MPACT transient calculations.