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

Abstract

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)

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Document Details

Document Type
Technical Report
Publication Date
Nov 27, 1979
Accession Number
ADA078135

Entities

People

  • A. I. Namenson
  • Michelle Rosen
  • R. A. Lindgren

Organizations

  • United States Naval Research Laboratory

Tags

Communities of Interest

  • Air Platforms
  • Energy and Power Technologies

DTIC Thesaurus Topics

  • Boltzmann Equation
  • Collisions
  • Distribution Functions
  • Energy
  • Estimators
  • Fast Neutrons
  • Geometry
  • Monte Carlo Method
  • Neutron Flux
  • Neutron Spectrum
  • Nuclear Reactors
  • Power Distribution
  • Pressure Vessels
  • Reactor Cores
  • Scattering
  • Spatial Distribution
  • Standards

Fields of Study

  • Physics

Readers

  • Combustion and Flow Dynamics.
  • Solar Physics