Version of the MORSE multigroup transport code for fusion reactors blankets and shields studies Metadata

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Title

  • Main Title Version of the MORSE multigroup transport code for fusion reactors blankets and shields studies

Creator

  • Author: Ragheb, M.M.
    Creator Type: Personal
  • Author: Maynard, C.W.
    Creator Type: Personal

Publisher

  • Name: Brookhaven National Laboratory
    Place of Publication: Upton, New York

Date

  • Creation: 1975-08-30

Language

  • English

Description

  • Physical Description: 29 p.

Subject

  • Keyword: Thermonuclear Reactors
  • Keyword: *Breeding Blankets-- Neutron Transport Theory
  • Keyword: *Shielding-- Neutron Transport Theory
  • Keyword: Gamma Radiation
  • Keyword: *Neutron Transport Theory-- Computer Codes
  • Keyword: Neutron Reactions
  • Keyword: N70800* --Physics--Controlled Thermonuclear Research-- Thermonuclear Engineering & Equipment
  • Keyword: Transport Theory
  • STI Subject Categories: 700201* --Fusion Energy--Fusion Power Plant Technology-- Blanket Engineering

Source

  • Other Information: Orig. Receipt Date: 31-DEC-75

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

  • Report No.: BNL--20376
  • Grant Number: None
  • DOI: 10.2172/4184695
  • Office of Scientific & Technical Information Report Number: 4184695
  • Archival Resource Key: ark:/67531/metadc865039

Note

  • Display Note: Dep. NTIS