DIFFUSE: a FORTRAN program for design computation of tritium transport through thermonuclear reactor components by combined ordinary and thermal diffusion when the principal resistance to diffusion is the bulk metal

Technical Report · Sat Oct 01 00:00:00 EDT 1977

DOI:https://doi.org/10.2172/5331611· OSTI ID:5331611

Pendergrass, J H

Based on the theory developed in an earlier report, a FORTRAN computer program, DIFFUSE, was written. It computes, for design purposes, rates of transport of hydrogen isotopes by temperature-dependent quasi-unidirectional, and quasi-static combined ordinary and thermal diffusion through thin, hot thermonuclear reactor components that can be represented by composites of plane, cylindrical-shell, and spherical-shell elements when the dominant resistance to transfer is that of the bulk metal. The program is described, directions for its use are given, and a listing of the program, together with sample problem results, is presented.

• Research Organization: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5331611
• Report Number(s): LA-7000-MS; TRN: 78-005048
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
COMPUTER CODES
D CODES
THERMONUCLEAR REACTOR MATERIALS
PERMEABILITY
TRITIUM
DIFFUSION
FORTRAN
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NUCLEI
ODD-EVEN NUCLEI
PROGRAMMING LANGUAGES
RADIOISOTOPES
YEARS LIVING RADIOISOTOPES
700206* - Fusion Power Plant Technology- Environmental Aspects