Zobrazeno 1 - 10
of 50
pro vyhledávání: '"Dan Kotlyar"'
Publikováno v:
Energies, Vol 17, Iss 13, p 3068 (2024)
Nuclear thermal propulsion is an evolving technology that can be utilized for long-distance space travel. This technology yields the advantage of a high thrust and specific impulse, but requires an examination of the potential design adjustments nece
Externí odkaz:
https://doaj.org/article/ee1124816cfc4bb9a16a64bc8c3d4569
Autor:
Matt Krecicki, Dan Kotlyar
Publikováno v:
Energies, Vol 15, Iss 19, p 7007 (2022)
Nuclear thermal propulsion is an enabling technology for future space missions, such as crew-operated Mars missions. Nuclear thermal propulsion technology provides a performance benefit over chemical propulsion systems by operating with light propell
Externí odkaz:
https://doaj.org/article/f4efe856e7414f1a9f81eae21abb223f
Publikováno v:
Metals, Vol 12, Iss 2, p 199 (2022)
Low-enriched-uranium (LEU) reactor systems utilize moderators to improve neutron economy. Solid yttrium hydride is one of the primary moderator candidates for high-temperature (>700 °C) nuclear reactor applications. This is due to its ability to ret
Externí odkaz:
https://doaj.org/article/b3fdec7acd3c4ae0b83aab877ab4f11c
Autor:
Robert Wilkerson, Dan Kotlyar, Michael W.D. Cooper, Sven C. Vogel, Dasari V. Rao, Vedant Mehta
Publikováno v:
Nuclear Science and Engineering. 195:563-577
Yttrium hydride is being considered as a moderator material for microreactor concepts because of its excellent hydrogen retainment capacity at high temperatures. These types of reactors, operating ...
Publikováno v:
Nuclear Science and Engineering. 194:1016-1024
The serpentTools Python package is presented as a useful and efficient alternative for processing Serpent results. One positive attribute of Serpent is that many output files are exported directly ...
Autor:
Dan Kotlyar, Stefano Terlizzi
Publikováno v:
Nuclear Science and Engineering. 194:280-296
Monte Carlo (MC) codes are widely used for the accurate modeling of nuclear reactors. However, efficient inclusion of thermal-hydraulic (TH) feedback within the MC calculation sequence is s...
Autor:
Dan Kotlyar, Naiki Kaffezakis
Publikováno v:
Nuclear Technology. 206:48-72
This paper details the development and optimization of a novel seed blanket fuel assembly designed for utilizing high-conversion Th-233U fuel cycles in the current fleet of pressurized wate...
Autor:
Dan Kotlyar, Stefano Terlizzi
Publikováno v:
Nuclear Science and Engineering. 193:948-965
This paper presents the theoretical foundations and the practical implementation of the Fission Matrix Decomposition (FMD) method. The FMD method is a hybrid technique for the rapid and acc...
Publikováno v:
Annals of Nuclear Energy 125(2019), 291-306
Recent developments of the reactor dynamics code DYN3D have introduced the micro-depletion model which allows for explicit calculation of radioactive decay heat. Such a unique combination of nodal diffusion, thermal hydraulic (T/H) and depletion solv
Autor:
Vedant Mehta, Dan Kotlyar
Publikováno v:
Annals of Nuclear Energy. 123:46-58
Fluoride High-temperature Reactors (FHRs) are regarded for their high temperature output and passive decay heat rejection. Small Modular Advanced High Temperature Reactor (SmAHTR), a 125 MWth reactor falls under the FHR group. Along with FHRs, SmAHTR