MCS–A Monte Carlo particle transport code for large-scale power reactor analysis
Abstract A new Monte Carlo (MC) neutron/photon transport code, called MCS, has been
developed at Ulsan National Institute of Science and Technology (UNIST) with the aim of …
developed at Ulsan National Institute of Science and Technology (UNIST) with the aim of …
High-fidelity multi-physics coupling study on advanced heat pipe reactor
The advanced heat pipe cooled reactor is a potential candidate to generate nuclear power
for space exploration, and exhibits strong neutron leakage and complicated multi-physics …
for space exploration, and exhibits strong neutron leakage and complicated multi-physics …
Depletion capabilities in the OpenMC Monte Carlo particle transport code
A depletion solver has been implemented in OpenMC and is described herein. The
depletion solver is implemented in Python and interfaces with OpenMC's transport solver …
depletion solver is implemented in Python and interfaces with OpenMC's transport solver …
A review of the current nuclear data performance assessments in advanced nuclear reactor systems
AA Ryzhkov, GV Tikhomirov, MY Ternovykh - Annals of Nuclear Energy, 2024 - Elsevier
There is a rise in sensitivity and uncertainty analyses with respect to nuclear data, which are
a basis for a neutron transport simulation. The analyses are primarily concerned with the …
a basis for a neutron transport simulation. The analyses are primarily concerned with the …
MCS based neutronics/thermal-hydraulics/fuel-performance coupling with CTF and FRAPCON
A Monte-Carlo neutronics/thermal-hydraulics/fuel-performance (N/TH/FP) multi-physics
coupling system has been developed based on the MCS code recently for the purpose of …
coupling system has been developed based on the MCS code recently for the purpose of …
[PDF][PDF] Initial development of PRAGMA–a GPU-based continuous energy Monte Carlo code for practical applications
▪ Vectorization (SIMD): A group of threads should perform same operations.▪ Memory
Coalescing: A group of threads should read and write contiguous memory.▪ Local Memory …
Coalescing: A group of threads should read and write contiguous memory.▪ Local Memory …
Release of windowed multipole library for ENDF/B-VIII. 0 in support of OpenMC criticality and depletion analysis
J Yu, B Forget - Progress in Nuclear Energy, 2024 - Elsevier
Major evaluations have been updated in the latest release of the Evaluated Nuclear Data
library (ENDF/B-VIII. 0) and is the currently recommended pointwise library for criticality and …
library (ENDF/B-VIII. 0) and is the currently recommended pointwise library for criticality and …
Windowed multipole representation of -matrix cross sections
Nuclear cross sections are basic inputs to any nuclear computation. Campaigns of
experiments are fitted with the parametric R-matrix model of quantum nuclear interactions …
experiments are fitted with the parametric R-matrix model of quantum nuclear interactions …
Fuel performance analysis of BEAVRS benchmark Cycle 1 depletion with MCS/FRAPCON coupled system
A fuel performance (FP) analysis of the BEAVRS (Benchmark for Evaluation and Validation
of Reactor Simulations) benchmark Cycle 1 depletion is performed using the …
of Reactor Simulations) benchmark Cycle 1 depletion is performed using the …
Definite complete invariant parametrization of -matrix theory
We establish a definite parametrization of R-matrix theory, which is complete and invariant.
Compared to the traditional parametrization of Wigner and Eisenbud, our parametrization …
Compared to the traditional parametrization of Wigner and Eisenbud, our parametrization …