OpenMC: A state-of-the-art Monte Carlo code for research and development
This paper gives an overview of OpenMC, an open source Monte Carlo particle transport
code recently developed at the Massachusetts Institute of Technology. OpenMC uses …
code recently developed at the Massachusetts Institute of Technology. OpenMC uses …
Current status of the reactor physics code WIMS and recent developments
BA Lindley, JG Hosking, PJ Smith, DJ Powney… - Annals of Nuclear …, 2017 - Elsevier
The WIMS modular reactor physics code has been under continuous development for over
fifty years. This paper discusses the current status of WIMS and recent developments, in …
fifty years. This paper discusses the current status of WIMS and recent developments, in …
[HTML][HTML] Spent nuclear fuel in dry storage conditions–current trends in fuel performance modeling
P Konarski, C Cozzo, G Khvostov… - Journal of Nuclear …, 2021 - Elsevier
The role of dry storage in spent nuclear fuel management becomes more and more
important. Originally intended to serve as a temporary solution for a few decades until final …
important. Originally intended to serve as a temporary solution for a few decades until final …
The virtual environment for reactor applications (VERA): design and architecture
VERA, the Virtual Environment for Reactor Applications, is the system of physics capabilities
being developed and deployed by the Consortium for Advanced Simulation of Light Water …
being developed and deployed by the Consortium for Advanced Simulation of Light Water …
[图书][B] Monte Carlo methods for particle transport
A Haghighat - 2020 - taylorfrancis.com
Fully updated with the latest developments in the eigenvalue Monte Carlo calculations and
automatic variance reduction techniques and containing an entirely new chapter on fission …
automatic variance reduction techniques and containing an entirely new chapter on fission …
MVP/GMVP Version 3. General purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods …
Y Nagaya, K Okumura, T Sakurai, T Mori - 2017 - inis.iaea.org
[en] In order to realize fast and accurate Monte Carlo simulation of neutron and photon
transport problems, two Monte Carlo codes MVP (continuous-energy method) and GMVP …
transport problems, two Monte Carlo codes MVP (continuous-energy method) and GMVP …
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 …
Development of high-fidelity neutron transport code STREAM
This paper presents a methodology developed and implemented in the neutron transport
code STREAM to perform high-fidelity, multicycle, multiphysics simulations of light water …
code STREAM to perform high-fidelity, multicycle, multiphysics simulations of light water …
MC21 v. 6.0–A continuous-energy Monte Carlo particle transport code with integrated reactor feedback capabilities
DP Griesheimer, DF Gill… - … MC 2013-Joint …, 2014 - sna-and-mc-2013-proceedings …
MC21 is a continuous-energy Monte Carlo radiation transport code for the calculation of the
steady-state spatial distributions of reaction rates in three-dimensional models. The code …
steady-state spatial distributions of reaction rates in three-dimensional models. The code …
Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code
The BEAVRS (Benchmark for Evaluation and Validation of Reactor Simulation) benchmark
is solved by the nTRACER direct whole core calculation code to assess its accuracy and to …
is solved by the nTRACER direct whole core calculation code to assess its accuracy and to …