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Analysis of Population Control Techniques for Time-Dependent and Eigenvalue Monte Carlo Neutron Transport Calculations

Journal Article · · Nuclear Science and Engineering
 [1];  [2]
  1. University of Notre Dame, Department of Aerospace and Mechanical Engineering, Notre Dame, Indiana 46556; OSTI
  2. University of Notre Dame, Department of Aerospace and Mechanical Engineering, Notre Dame, Indiana 46556

Not provided.

Research Organization:
Oregon State Univ., Corvallis, OR (United States); Center for Exascale Monte-Carlo Neutron Transport (CEMeNT) (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
DOE Contract Number:
NA0003967
OSTI ID:
2417764
Journal Information:
Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 11 Vol. 196; ISSN 0029-5639
Publisher:
Taylor & Francis
Country of Publication:
United States
Language:
English

References (20)

Sur les fonctions convexes et les inégalités entre les valeurs moyennes journal January 1906
New kinetic simulation capabilities for Tripoli-4®: Methods and applications journal October 2018
A Particle Population Control Method for Dynamic Monte Carlo conference January 2014
The Serpent Monte Carlo code: Status, development and applications in 2013 journal August 2015
G4-STORK: A Monte Carlo Reactor Kinetics Simulation Code journal March 2014
Monte Carlo Application ToolKit (MCATK) journal August 2015
OpenMC: A state-of-the-art Monte Carlo code for research and development journal August 2015
Multigroup Constant Calculation with Static α-Eigenvalue Monte Carlo for Time-Dependent Neutron Transport Simulations journal June 2020
Developing and investigating a pure Monte-Carlo module for transient neutron transport analysis journal June 2017
Hybrid Deterministic/Monte Carlo Neutronics journal January 2013
Dynamic Monte Carlo transient analysis for the Organization for Economic Co-operation and Development Nuclear Energy Agency (OECD/NEA) C5G7-TD benchmark journal August 2017
A GPU-based direct Monte Carlo simulation of time dependence in nuclear reactors journal October 2019
mpi4py: Status Update After 12 Years of Development journal July 2021
Four Decades of Implicit Monte Carlo journal September 2015
TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code journal August 2015
Dynamic Monte Carlo Method for Nuclear Reactor Kinetics Calculations journal September 2013
Estimation of time-dependent neutron transport from point source based on Monte Carlo power iteration journal June 2019
Parallel Fission Bank Algorithms in Monte Carlo Criticality Calculations journal February 2012
A pure dynamic Monte Carlo code for the neutronic analysis of nuclear reactors journal January 2022
The Green's function method for effective multiplication benchmark calculations in multi-region slab geometry journal September 2004

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