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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Junli Li, Shenjin Ming, Yanfeng Cao, Yanli Deng
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 391-398
Shielding | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9215
Articles are hosted by Taylor and Francis Online.
The X-ray container/vehicle inspection system is a large and complex radiation application facility. To evaluate and optimize the shielding design for the system, a Monte Carlo method including two-step simulation, biasing sampling, and a scattering flag technique has been used to perform the shielding analysis - instead of the traditional empirical formula calculation.When the Monte Carlo method is applied to a complicated large system, some special techniques shall be used to obtain high accuracy and high efficiency in calculation. A special Monte Carlo method based on Geant4, including two-step simulation, biasing sampling, and scattering flag techniques, has been developed in this paper. For the two-step simulation, the first step is to simulate the electron transport inside the tungsten target of a linac and generate X-ray photons; the second step is to simulate the X-ray photon transport in the inspection system. For the biasing sampling, only the photons inside the X-ray beam are simulated and tracked. This allows more photons to reach the inspection system boundary. For the scattering flag, the trace of every photon reaching the inspection system boundary is recorded and stored, thus providing the possibility to tag the main dose contributors to the system boundary and allowing optimization of the shielding design.The simulation results on the inspection system boundary agree well with the measured results, and the key radiation contributors to the radiation dose on the system boundary are found with the scattering flag technique.A special Monte Carlo method combined with two-step simulation, biasing sampling and scattering flag techniques, has been developed and successfully used in the shielding design and optimization in an X-ray container/vehicle inspection system.