A Diffusion-Accelerated Sn Transport Method for Radiation Transport on a General Quadrilateral Mesh-Reference-Cited by-同舟云学术

A Diffusion-Accelerated Sn Transport Method for Radiation Transport on a General Quadrilateral Mesh

Published:1990-06 Issue:2 Volume:105 Page:191-197
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Alcouffe R. E.¹

Affiliation:

1. Los Alamos National Laboratory, X-6, MS B226, Los Alamos, New Mexico 87545

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE90-A23748

Reference5 articles.

1. R. D. O’DELL and R. E. ALCOUFFE, “Transport Calculations for Nuclear Analysis: Theory and Guidelines for Effective Use of Transport Codes,” LA-10983-MS, Los Alamos National Laboratory (1987).

2. R. E. ALCOUFFE, F. W. BRINKLEY, D. R. MARR, and R. D. O’DELL, “User’s Guide for TWODANT: A Code Package for Two-Dimensional, Diffusion-Accelerated Neutral Particle Transport,” LA-10049-M, Los Alamos National Laboratory (1984).

3. E. W. LARSEN, University of Michigan, Private Communication (1989).

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