Monte Carlo Methods for Neutron Flux Calculations in a Pressurized Light Water Power Reactor Using Morse-CG

Various methods of optimizing Monte Carlo calculations of fast flux and spectra in a pressurized light water reactor are investigated using the code MORSE. Results in slab and cylindrical geometry are compared with those of the code ANISN. (Author)

Saved in:
Bibliographic Details
Main Authors: Lindgren ,R A, Rosen ,M, Namenson,A I
Format: Report
Language:English
Subjects:
COMPUTERIZED SIMULATION
FAST NEUTRONS
Fission Reactor Physics
LIGHT WATER REACTORS
MATHEMATICAL MODELS
MONTE CARLO METHOD
NEUTRON FLUX
Nuclear Fission Reactors(power)
Numerical Mathematics
PE61153N
WUH0180
Online Access:Request full text
Tags: Add Tag
No Tags, Be the first to tag this record!
Description
Summary:Various methods of optimizing Monte Carlo calculations of fast flux and spectra in a pressurized light water reactor are investigated using the code MORSE. Results in slab and cylindrical geometry are compared with those of the code ANISN. (Author)