Development of Neutronics Evaluation and Analysis Capabilities for Fusion Reactor Facilities [PDF]
This dissertation outlines the development of advanced neutronics evaluation and analysis techniques for fusion reactor facilities, focusing on the Fusion Energy System Studies-Fusion Nuclear Science Facility (FESS-FNSF) conceptual design.
Rizk, Marina
core +1 more source
Extension of OpenMC for Fixed Source Transmutation Calculations [PDF]
, 2020 openaire +1 more source
Prediction and assessment of optimal concrete compositions for overall radiation protection and reduced global warming potential. [PDF]
Sci RepSaxena S, Sharma H.
europepmc +1 more source
Point containment algorithms for constructive solid geometry with unbounded primitives
We present several algorithms for evaluating point containment in constructive solid geometry (CSG) trees with unbounded primitives. Three algorithms are presented based on postfix, prefix, and infix notations of the CSG binary expression tree.
Johnson, Seth R. +4 more
core
ZED-2 benchmarks performed in OpenMC and Serpent 2: A validation exercise for OpenMC applications
Annals of Nuclear EnergyPeter J. Kriemadis, Adriaan Buijs
openaire +1 more source
Burning fuel for cheap! Transport-independent depletion in OpenMC
We have added functionality for running depletion simulations independently of neutron transport in OpenMC, an open source Monte Carlo particle transport code with an internal depletion module. Transport-independent depletion uses pre-computed static multigroup cross sections and fluxes to calculate reaction rates for OpenMC's depletion matrix solver ...
Yardas, Oleksandr +3 more
openaire +2 more sources
Neutronics design of shutdown and control systems for a Zero Power Experiments of chloride-based molten salt fast reactor. [PDF]
PLoS OneJain L +5 more
europepmc +1 more source
A multidisciplinary framework from reactors to repositories for evaluating spent nuclear fuel from advanced reactors. [PDF]
Sci RepWainwright HM +6 more
europepmc +1 more source
Non-uniform fuel distribution and thermo-mechanical analysis of a 1 MW thermal power micronuclear heat pipe reactor. [PDF]
HeliyonAziz U, Koreshi ZU, Khan H, Sheikh SR.
europepmc +1 more source
Digital: accelerating the pathway. [PDF]
Philos Trans A Math Phys Eng SciDavis A +6 more
europepmc +1 more source