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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.
Magdi M. H. Ragheb, Gregory A. Moses, Charles W. Maynard
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 16-33
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32444
Articles are hosted by Taylor and Francis Online.
Pellet and coupled pellet-blanket time-integrated neutronics and photonics calculations are reported for a representative low-gain (25), low-compression (deuterium-tritium core ρr = 9.4 kg/m2) pellet design for an electron beam fusion reactor. Tungsten, lead, and natural uranium are compared as pusher-tamper materials. In the three cases, neutron balances show that neutron multiplication in the pellet compensates for the energy losses and spectral softening due to neutron interactions. Fissile breeding cannot be achieved in the natural uranium case, since the fission reaction predominates. Substantive additional energy can be obtained (∼5.5 MeV/source neutron) in the pellet if natural uranium is used as the tamper material. Neutron and gamma spectra from the pellet micro explosions are given. Natural uranium, tungsten, and lead cause 14, 7, and 4% neutron multiplication, respectively. Compared to the case where a pure 14.1-MeV source is used, the spectra for the lead and tungsten pellets lead to almost the same values of breeding and heating rates. However, these are apportioned differently between the 7Li(n,α) and 7Li(n,n’α) reactions and spatial positions in the blanket. The atomic displacements and the gas production per unit of thermal power produced at the first wall are substantially reduced in the natural uranium case. Natural uranium as a tamper material leads to 8% higher tritium breeding and a 39% increase in energy production compared to the tungsten case. Per unit of energy produced, it leads to 27% less displacement damage and 30%) less hydrogen and helium production than the tungsten pellet case. For larger ρr values, these effects may be more pronounced. These results indicate that longer wall lifetimes may be obtained by neutron spectrum softening in the pellet without affecting the breeding and heat production in the blanket.