Results 21 to 30 of about 898 (171)

High‐Fidelity Monte Carlo Analysis of Highly‐Localized Fission Power Peaking near a Flux Trap in an MTR Core

International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023
In this study, a high‐fidelity Monte Carlo model was utilized to investigate the localized behavior of the power peaking factor in a reactor core. The model considered the effect of water gaps, also known as flux traps, on the local power peaking.
Hadi Abuzlf, Christian Castagna, Tzach Makmal, Ofer Aviv, Zohar Yungrais, Guy Gabrieli, Uri Steinitz, Izhar Neder, Erez Gilad, Sathish K. Kamaraj   +9 more
wiley   +1 more source

Modeling and simulation of VERA core physics benchmark using OpenMC code

Nuclear Engineering and Technology, 2023
Detailed analysis of the neutron pathway through matter inside the nuclear reactor core is exceedingly needed for safety and economic considerations. Due to the constant development of high-performance computing technologies, neutronics analysis using ...
Abdullah O. Albugami, Abdullah S. Alomari, Abdullah I. Almarshad   +2 more
doaj   +1 more source

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

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

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

Accelerated sampling of the free gas resonance elastic scattering kernel [PDF]

, 2013
In this work, we present the derivation and investigation of a new Doppler broadening rejection sampling approach for the exact treatment of resonance elastic scattering in Monte Carlo neutron transport codes. Implemented in OpenMC, this method correctly
Forget, Benoit Robert Yves, Smith, Kord S., Walsh, Jonathan Alan   +2 more
core   +1 more source

Multi-core performance studies of a Monte Carlo neutron transport code [PDF]

, 2013
Performance results are presented for a multi-threaded version of the OpenMC Monte Carlo neutronics code using OpenMP in the context of nuclear reactor criticality calculations. Our main interest is production computing, and thus we limit our approach to
Felker, K. G., Forget, Benoit Robert Yves, Romano, Paul Kollath, Siegel, A. R., Smith, Kord S.   +4 more
core   +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