AN ANALYTICAL APPROACH FOR THE COMBINED AGE-DIFFUSION EQUATION

Journal Article · Tue Oct 01 00:00:00 EDT 1963 · Denki Shikensho Iho (Japan) Changed to Denshi Gijutsu Sogo Kenkyusho Iho

OSTI ID:4003413

Amano, F

An analytic method is developed for the solution of the multiregion reactor system. The neutron fluxes are expanded in a series of eigenfunctions which are solutions of the Helmholtz equation, the eigenvalue problem is derived from the equation satisfied by these expansion coefficients, and thus the criticality condition considering completely the fast-neutron-flux space dependence is de nlved. This method is developed for one- and two-dimensional problems. As an example, calculations for a fictitious slab reactor are made on the IBM-7090 and ETL Mark V. (auth)

• Research Organization: Electrotechnical Lab., Tokyo
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: NONE
• NSA Number: NSA-18-021603
• OSTI ID: 4003413
• Journal Information: Denki Shikensho Iho (Japan) Changed to Denshi Gijutsu Sogo Kenkyusho Iho, Journal Name: Denki Shikensho Iho (Japan) Changed to Denshi Gijutsu Sogo Kenkyusho Iho Vol. Vol: 27; ISSN DESIA
• Country of Publication: Country unknown/Code not available
• Language: Japanese

Related Subjects

COMPUTERS
CRITICALITY
DIFFERENTIAL EQUATIONS
DIFFUSION
DIGITAL SYSTEMS
DISTRIBUTION
EIGENFUNCTIONS
EIGENVALUES
EQUATIONS
FAST NEUTRONS
FERMI AGE
HELMHOLTZ EQUATION
IBM 7090
MATHEMATICS
NEUTRON FLUX
NEUTRONS
Nuclear Criticality Safety Program (NCSP)
PLATES
REACTOR TECHNOLOGY
REACTORS
ZONES