A Nodal Method for Solving Transient Fewgroup Neutron Diffusion Equations

One of 1,237 reports in the series: Argonne National Laboratory Reports available on this site.

PDF Version Also Available for Download.

Description

A nodal method for multidimensional light water reactor (LWR) static and transient analysis is presented in this report. This method efficiently solves one- or two-group diffusion equations using an analytic solution procedure. This report details significant improvements made to those aspects of the method previously reported in the literature. Eigenvalues and power distributions are presented for several static benchmark problems. Time-dependent results for a difficult two-dimensional BWR kinetics benchmark problem are presented. A reference solution for this benchmark problem is also presented. The results presented in this report are summarized, and suggestions are made as to appropriate ways to extend ... continued below

Physical Description

82 p. : charts

Creation Information

Shober, R. A. June 1978.

Context

This report is part of the collection entitled: Technical Report Archive and Image Library and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 63 times . More information about this report can be viewed below.

Who

People and organizations associated with either the creation of this report or its content.

Author

Publisher

Audiences

We've identified this report as a primary source within our collections. Researchers, educators, and students may find this report useful in their work.

Provided By

UNT Libraries Government Documents Department

Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.

Contact Us

What

Descriptive information to help identify this report. Follow the links below to find similar items on the Digital Library.

Titles

  • Main Title: A Nodal Method for Solving Transient Fewgroup Neutron Diffusion Equations
  • Added Title: ANL (Series)
  • Added Title: Argonne National Laboratory Report ANL-78-51
  • Series Title: Argonne National Laboratory Reports

Description

A nodal method for multidimensional light water reactor (LWR) static and transient analysis is presented in this report. This method efficiently solves one- or two-group diffusion equations using an analytic solution procedure. This report details significant improvements made to those aspects of the method previously reported in the literature. Eigenvalues and power distributions are presented for several static benchmark problems. Time-dependent results for a difficult two-dimensional BWR kinetics benchmark problem are presented. A reference solution for this benchmark problem is also presented. The results presented in this report are summarized, and suggestions are made as to appropriate ways to extend this work to multi-group fast breeder reactor analysis.

Physical Description

82 p. : charts

Notes

Digitized from microfiche (1).

Some parts of this report may be illegible, depending on the quality of the microfiche.

Language

Item Type

Identifier

Unique identifying numbers for this report in the Digital Library or other systems.

  • OCLC: 883330307 | External Link
  • SuDoc Number: E 1.28:ANL-78-51
  • SuDoc Number: Y 3.AT 7:22/ANL-78-51
  • Report No.: ANL-78-51
  • Grant Number: W-31-109-Eng-38
  • Archival Resource Key: ark:/67531/metadc303752

Collections

This report is part of the following collection of related materials.

Technical Report Archive and Image Library

This selection of materials from the Technical Report Archive and Image Library (TRAIL) includes hard-to-find reports published by various government agencies. The technical publications contain reports, images, and technical descriptions of research performed for U.S. government agencies. Topics range from mining, desalination, and radiation to broader physics, biology, and chemistry studies. Some reports include maps, foldouts, blueprints, and other oversize materials.

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • June 1978

Added to The UNT Digital Library

  • Aug. 4, 2015, 8:33 a.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 1
Total Uses: 63

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

International Image Interoperability Framework

IIF Logo

We support the IIIF Presentation API

Shober, R. A. A Nodal Method for Solving Transient Fewgroup Neutron Diffusion Equations, report, June 1978; Argonne, Illinois. (digital.library.unt.edu/ark:/67531/metadc303752/: accessed December 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.