Effect of /sup 235/U concentration on fast neutron space and time eigenvalues and eigenfunctions in uranium

Journal Article · Wed May 01 00:00:00 EDT 1985 · Nucl. Sci. Eng.; (United States)

OSTI ID:5129149

Mohan, R; Ahmed, F; Kothari, L S

The results of a detailed study of a fast neutron diffusion length and pulsed problem in depleted and enriched subcritical uranium assemblies (0.2 to 4% /sup 235/U) are reported. The multigroup space- and time-dependent equations are solved using the eigenfunction expansion method. The effect of /sup 235/U concentration on space (diffusion length problem) and time (pulsed problem) eigenvalues and eigenfunctions, particularly on the ''discrete'' eigenvalue and eigenfunction, is discussed. The approach to equilibrium (both in space and in time) of fast neutrons changes with changing /sup 235/U concentration.

• Research Organization: University of Delhi, A.R.S.D. College, New Delhi
• OSTI ID: 5129149
• Journal Information: Nucl. Sci. Eng.; (United States), Vol. 90:1
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
SLIGHTLY ENRICHED URANIUM
EIGENFUNCTIONS
EIGENVALUES
CALCULATION METHODS
CRITICALITY
DIFFUSION LENGTH
FAST NEUTRONS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
RADIOACTIVITY
REACTOR CORES
REACTOR KINETICS
SPACE DEPENDENCE
SUBCRITICAL ASSEMBLIES
TIME DEPENDENCE
URANIUM 235
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALPHA DECAY RADIOISOTOPES
BARYONS
DIFFERENTIAL EQUATIONS
DIMENSIONS
ELEMENTARY PARTICLES
ELEMENTS
ENRICHED URANIUM
EQUATIONS
EVEN-ODD NUCLEI
EXPERIMENTAL REACTORS
FERMIONS
FUNCTIONS
HADRONS
HEAVY NUCLEI
ISOMERIC TRANSITION ISOTOPES
ISOTOPE ENRICHED MATERIALS
ISOTOPES
KINETICS
LENGTH
MATERIALS
METALS
MINUTES LIVING RADIOISOTOPES
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEI
NUCLEONS
RADIOISOTOPES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
TRANSPORT THEORY
URANIUM
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
050700* - Nuclear Fuels- Fuels Production & Properties
220100 - Nuclear Reactor Technology- Theory & Calculation