Results 91 to 100 of about 898 (171)

CAD and constructive solid geometry modeling of the Molten Salt Reactor Experiment with OpenMC

Frontiers in Nuclear Engineering
In this study, we present a detailed comparison of two independently developed models of the Molten Salt Reactor Experiment (MSRE) for Monte Carlo particle transport simulations: the constructive solid geometry (CSG) model that was developed in support ...
Seda Yilmaz, Paul K. Romano, Lorenzo Chierici, Erik B. Knudsen, Patrick C. Shriwise   +4 more
doaj   +1 more source

Transmutation of MAs and LLFPs with a lead-cooled fast reactor. [PDF]

Sci Rep, 2023
Sun XY, Han LH, Li XX, Hu BL, Luo W, Liu L.   +5 more
europepmc   +1 more source

Multi-step verification of the Copenhagen atomics molten salt experiment radioactive inventory at the Paul Scherrer Institute using OpenMC, Serpent, and EQL0D

Frontiers in Nuclear Engineering
The molten salt experiment (MSE) is a 30-day 1 MW (thermal) molten salt criticality experiment designed by Copenhagen Atomics that will be conducted at the Paul Scherrer Institute (PSI) Swiss research center.
Lorenzo Chierici, Alessio Rossi
doaj   +1 more source

Demonstration of OpenMC as a framework for atomic transport and plasma interaction

Plasma Physics and Controlled Fusion
Abstract Modern tooling is demanded for predicting the transport and reaction characteristics of atoms and molecules, especially in the context of magnetic confinement fusion. DEGAS2, among the most common and capable tools currently in use, shares many fundamental similarities with the OpenMC framework, which was primarily developed for
G J Wilkie, P K Romano, R M Churchill
openaire   +2 more sources

The Paramak: automated parametric geometry construction for fusion reactor designs. [PDF]

F1000Res, 2021
Shimwell J, Billingsley J, Delaporte-Mathurin R, Morbey D, Bluteau M, Shriwise P, Davis A.   +6 more
europepmc   +1 more source

Multiscale computational study to predict the irradiation-induced change in engineering properties of fusion reactor materials

Nuclear Materials and Energy
In this study, we address the impact of irradiation conditions in a tokamak on the engineering properties of materials, leading to potential degradation of in-vessel components over their lifecycle.
Salahudeen Mohamed, Giacomo Po, Rhydian Lewis, Perumal Nithiarasu   +3 more
doaj   +1 more source

What Are Polymorphically-Typed Ambients? [PDF]

: The Ambient Calculus was developed by Cardelli and Gordon as a formal framework to study issues of mobility and migrant code. We consider an Ambient Calculus where ambients transport and exchange programs rather that just inert data.
Amtoft, Torben, Kfoury, Assaf J., Pericas-Geertsen, Santiago M.   +2 more
core  

Application of LoongSARAX in Calculation of Plate Fuel Critical Experimental Facility

Yuanzineng kexue jishu
As the main type of fast reactor in the future development of nuclear energy, neutron calculation is very important for core design and safety analysis.
LI Zehua1, ZHANG Qian2, DU Xianan3, ZHAO Changyou1
doaj   +1 more source

Development and validation of fully open-source R2S shutdown dose rate capabilities in OpenMC

Nuclear Fusion
We present the first fully open-source capabilities for shutdown dose rate (SDR) calculations of fusion energy facilities based on the Rigorous 2-Step (R2S) methodology.
Ethan E. Peterson, Paul K. Romano, Patrick C. Shriwise, Patrick A. Myers   +3 more
doaj   +1 more source

Nuclear and radiological characterization of a 226Ra-Be neutron irradiator at INFISA-UNMSM, Peru, using Monte Carlo simulation with the OpenMC code

Nuclear Engineering and Technology
A neutron irradiator consisting of a226Ra-Be source with a 3 mCi activity of radium, used for the early teaching of neutron activation experiments, belonging to the INFISA-UNMSM, was characterized using the relatively new open-source framework OpenMC ...
P. Tataje, Abdessamad Didi, A. Arroyo, S. Daza   +3 more
doaj   +1 more source