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NEUTRON DIFFUSION IN A SPACE LATTICE OF FISSIONABLE AND ABSORBING MATERIALS

Description/Abstract

Methods are developed for estimating the effect on a critical assembly of fabricating it as a lattice rather than in the more simply interpreted homogeneous manner. An idealized case is discussed supposing an infinite medium in which fission, elastic scattering and absorption can occur, neutrons of only one velocity present, and the neutron m.f.p. independent of position and equal to unity with the unit of length use. (auth)

Authors: Welton, T.A.; Feynman, R.P.
Publication Date:1946 Aug 27
OSTI Identifier: 4381097
Report Number(s):LA-603
DOE Contract Number:W-7405-ENG-36
Resource Type:Technical Report
Resource Relation: Decl. Dec. 16, 1955; PBD: 27 Aug 1946
Research Org:Los Alamos Scientific Lab., N. Mex. (US)
Sponsoring Org:US Atomic Energy Commission (AEC) (US)
Country of Publication:United States
Language:English
Format: Size: : 21 pages
Other Number(s):TRN: US200506%%309
Subject:11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CRYSTAL LATTICES; ELASTIC SCATTERING; ABSORPTION; CONFIGURATION; ZERO POWER REACTORS; CRITICALITY; CROSS SECTIONS; DIFFUSION; DIFFUSION LENGTH; FISSION; FISSIONABLE MATERIALS; GROUP THEORY; MATHEMATICS; MEAN FREE PATH; NEUTRONS; REACTORS; SCATTERING; VELOCITY
Availability:NTIS; OSTI as DE04381097
Update Date:2008 Feb 05

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