AbstractBecause of prohibitive data storage requirements in large-scale simulations, the memory problem is an obstacle for Monte Carlo (MC) codes in accomplishing pin-wise three-dimensional (3D) full-core calculations, particularly for whole-core depletion analyses. Various kinds of data are evaluated and quantificational total memory requirements are analyzed based on the Reactor Monte Carlo (RMC) code, showing that tally data, material data, and isotope densities in depletion are three major parts of memory storage. The domain decomposition method is investigated as a means of saving memory, by dividing spatial geometry into domains that are simulated separately by parallel processors. For the validity of particle tracking during transpor...
For several years, Monte Carlo burnup/depletion codes have appeared, which couple Monte Carlo codes ...
This paper presents a whole-core depletion analysis of Yonggwang Unit 3, cycles 1 and 2, by using MC...
The theoretical aspects behind the reactor depletion capability of the Monte Carlo code MCS develope...
AbstractBecause of prohibitive data storage requirements in large-scale simulations, the memory prob...
The applications of Monte Carlo method in reactor physics analysis is somewhat restricted due to exc...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
Monte Carlo (MC) neutral particle transport codes are considered the gold-standard for nuclear simul...
To examine the domain decomposition code coupled Monte Carlo-finite element calculation, it is impor...
Several computer codes have been developed to perform nuclear burnup calculations over the past few ...
An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is devel...
For several years, Monte Carlo burnup/depletion codes have appeared, which couple Monte Carlo codes ...
Achieving parallelism in simulations that use Monte Carlo transport methods presents interesting cha...
A whole-core depletion analysis of OPR-1000 using MCS coupled with FRAPCON is presented in this pape...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
Monte Carlo neutron transport codes are a growing subject of research in nuclear reactor analysis. F...
For several years, Monte Carlo burnup/depletion codes have appeared, which couple Monte Carlo codes ...
This paper presents a whole-core depletion analysis of Yonggwang Unit 3, cycles 1 and 2, by using MC...
The theoretical aspects behind the reactor depletion capability of the Monte Carlo code MCS develope...
AbstractBecause of prohibitive data storage requirements in large-scale simulations, the memory prob...
The applications of Monte Carlo method in reactor physics analysis is somewhat restricted due to exc...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
Monte Carlo (MC) neutral particle transport codes are considered the gold-standard for nuclear simul...
To examine the domain decomposition code coupled Monte Carlo-finite element calculation, it is impor...
Several computer codes have been developed to perform nuclear burnup calculations over the past few ...
An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is devel...
For several years, Monte Carlo burnup/depletion codes have appeared, which couple Monte Carlo codes ...
Achieving parallelism in simulations that use Monte Carlo transport methods presents interesting cha...
A whole-core depletion analysis of OPR-1000 using MCS coupled with FRAPCON is presented in this pape...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
Monte Carlo neutron transport codes are a growing subject of research in nuclear reactor analysis. F...
For several years, Monte Carlo burnup/depletion codes have appeared, which couple Monte Carlo codes ...
This paper presents a whole-core depletion analysis of Yonggwang Unit 3, cycles 1 and 2, by using MC...
The theoretical aspects behind the reactor depletion capability of the Monte Carlo code MCS develope...