Results 31 to 40 of about 538 (156)

csg2csg: A TOOL TO ASSIST VALIDATION & VERIFICATION [PDF]

EPJ Web of Conferences, 2021
The csg2csg tool is a minimal dependency Python3 based program to facilitate the comparison of radiation transport Monte Carlo codes. The csg2csg can currently parse MCNP and OpenMC geometry descriptions, and it can subsequently export MCNP, FLUKA, PHITS,
Davis Andrew, Lilley Steven, Shimwell Jonthan   +2 more
doaj   +1 more source

Development and benchmarking of a point detector in OpenMC

Annals of Nuclear Energy
Tsviki Y Hirsh
exaly   +2 more sources

openmc-dev/openmc: OpenMC 0.13.2

, 2022
This release of OpenMC includes several bug fixes, performance improvements for complex geometries and depletion simulations, and other general enhancements.
Isaac Meyer, Jiankai, Lewis Gross, Kalin Kiesling, Olek, Jonathan Shimwell, John Tramm, YoungHui Park, Patrick Myers, Andrew Johnson, Zhuoran Han, helen-brooks, sam, Ethan Peterson, Jingang Liang, April Novak, dryuri92, Nicholas Horelik, Travis L., Amanda Lund, Josh May, Erik B Knudsen, Guillaume Giudicelli, Olaf Schumann, Gavin Ridley, Miriam Kreher, Sterling Harper, Andrew Davis, Adam Nelson, Patrick Shriwise, Rémi Delaporte-Mathurin, Paul Romano   +31 more
core   +1 more source

NEUTRONIC BENCHMARK ON HOLOS-QUAD MICRO-REACTOR CONCEPT [PDF]

EPJ Web of Conferences, 2021
The Holos-Quad micro-reactor concept is proposed by HolosGen LLC for civilian applications to generate 22 MWt with a lifetime of approximately 8 effective full power years (EFPYs).
Stauff N. E., Lee C. H., Shriwise P., Wells A., Filippone C.   +4 more
doaj   +1 more source

openmc-dev/openmc: OpenMC 0.12.1

, 2021
This release of OpenMC includes an assortment of new features and many bug fixes. The openmc.deplete module incorporates a number of improvements in usability, accuracy, and performance. Other enhancements include generalized rotational periodic boundary
Isaac Meyer, Jiankai, Cyrus Wyett, Jonathan Shimwell, DanShort12, John Tramm, YoungHui Park, Andrew Johnson, Zhuoran Han, sam, Ethan Peterson, Mikolaj-A-Kowalski, Jingang Liang, dryuri92, April Novak, Nicholas Horelik, Travis L., Amanda Lund, shikhar413, Guillaume Giudicelli, Gavin Ridley, davidjohnlong, Miriam Kreher, Colin Josey, Sterling Harper, Andrew Davis, Ariful Islam Pranto, Adam Nelson, Patrick Shriwise, Paul Romano   +29 more
core   +1 more source

Development of transient Monte Carlo in a fissile system with β-delayed emission from individual precursors using modified open source code OpenMC(TD)

Nuclear Engineering and Technology, 2023
In deterministic and Monte Carlo transport codes, β-delayed emission is included using a group structure where all of the precursors are grouped together in 6 groups or families, but given the increase in computational power, nowadays there is no reason ...
J. Romero-Barrientos, F. Molina, J.I. Márquez Damián, M. Zambra, P. Aguilera, F. López-Usquiano, S. Parra   +6 more
doaj   +1 more source

Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core

Science and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 2020
The thermal hydraulic and neutronics coupling analysis is an important part of the high‐fidelity simulation for nuclear reactor core. In this paper, a thermal hydraulic and neutronics coupling method was proposed for the plate type fuel reactor core based on the Fluent and Monte Carlo code.
Linrong Ye, Mingjun Wang, Xin’an Wang, Jian Deng, Yan Xiang, Wenxi Tian, Suizheng Qiu, G. H. Su, Fu Li   +8 more
wiley   +1 more source

Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests

Nuclear Engineering and Technology, 2022
High-fidelity nuclear data libraries and neutronics simulation tools are essential for the development of fast reactors. The IAEA coordinated research project on “Neutronics Benchmark of CEFR Start-Up Tests” offers valuable data for the qualification of ...
Hui Guo, Xingkai Huo, Kuaiyuan Feng, Hanyang Gu   +3 more
doaj   +1 more source

Radiation damage and yield strength calculations in the pressure vessel of WWER-1000 reactor and sensitivity analysis of neutron spectrum on the shield of vessel [PDF]

مجله علوم و فنون هسته‌ای, 2021
Radiation damage calculation is very important for estimating the lifetime of nuclear power plant instruments. The purpose of the present study is to evaluate the sensitivity of the damage values to the neutron group energy, where the neutron flux rate ...
E. Moslemi-Mehni, F. Khoshahval, R. Pour-Imani, M. A. Amirkhani-Dehkordi   +3 more
doaj   +1 more source

Upsampling Monte Carlo neutron transport simulation tallies using a convolutional neural network

Energy and AI, 2023
The physical quantities calculated by nuclear reactor Monte Carlo simulations are typically recorded on a grid of two or three spatial dimensions and one dimension of neutron energy. Because of this, increasing the resolution of the calculated quantities
Andrew Osborne, Joffrey Dorville, Paul Romano   +2 more
doaj   +1 more source