A bibliography on finite element and related methods analysis in reactor physics computations (1971--1997) Metadata

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Title

  • Main Title A bibliography on finite element and related methods analysis in reactor physics computations (1971--1997)

Creator

  • Author: Carpenter, D.C.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Office of the Assistant Secretary for Nuclear Energy.
    Contributor Type: Organization
    Contributor Info: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)

Publisher

  • Name: Bettis Atomic Power Laboratory
    Place of Publication: West Mifflin, Pennsylvania
    Additional Info: Bettis Atomic Power Lab., West Mifflin, PA (United States)

Date

  • Creation: 1998-01-01

Language

  • English

Description

  • Content Description: This bibliography provides a list of references on finite element and related methods analysis in reactor physics computations. These references have been published in scientific journals, conference proceedings, technical reports, thesis/dissertations and as chapters in reference books from 1971 to the present. Both English and non-English references are included. All references contained in the bibliography are sorted alphabetically by the first author`s name and a subsort by date of publication. The majority of the references relate to reactor physics analysis using the finite element method. Related topics include the boundary element method, the boundary integral method, and the global element method. All aspects of reactor physics computations relating to these methods are included: diffusion theory, deterministic radiation and neutron transport theory, kinetics, fusion research, particle tracking in finite element grids, and applications. For user convenience, many of the listed references have been categorized. The list of references is not all inclusive. In general, nodal methods were purposely excluded, although a few references do demonstrate characteristics of finite element methodology using nodal methods (usually as a non-conforming element basis). This area could be expanded. The author is aware of several other references (conferences, thesis/dissertations, etc.) that were not able to be independently tracked using available resources and thus were not included in this listing.
  • Physical Description: 75 p.

Subject

  • Keyword: Information Systems
  • Keyword: Neutron Diffusion Equation
  • Keyword: Neutron Transport Theory
  • STI Subject Categories: 99 Mathematics, Computers, Information Science, Management, Law, Miscellaneous
  • Keyword: Calculation Methods
  • Keyword: Reactor Physics
  • Keyword: Finite Element Method
  • STI Subject Categories: 22 Nuclear Reactor Technology
  • Keyword: Bibliographies

Source

  • Other Information: PBD: Jan 1998

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • Other: DE98003127
  • Report No.: WAPD-TM--1635
  • Grant Number: AC11-93PN38195
  • DOI: 10.2172/569133
  • Office of Scientific & Technical Information Report Number: 569133
  • Archival Resource Key: ark:/67531/metadc693294

Note

  • Display Note: OSTI as DE98003127
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