Generalized subgroup approach to calculating the resonant absorption of neutrons

Journal Article · Sat Feb 01 04:00:00 UTC 1986 · Sov. At. Energy (Engl. Transl.); (United States)

OSTI ID:5664827

Tebin, V V; Yudkevich, M S

A subgroup equation of neutron transfer valid for resonances of arbitrary width is formulated. The problem of obtaining subgroup parameters in the approximation of a constant (in units of lethargy) collision density for neutrons of a single subgroup is considered. The BNAB constants, widely used for fast reactors, may also be used for thermal reactors. The generalized subgroup approach outlined here is convenient for computer realization on account of this single method of solution in the regions of unresolved and resolved resonances and the presence of a sufficiently complete library of constants. At the same time, this approach is also sufficiently economical.

• OSTI ID: 5664827
• Journal Information: Sov. At. Energy (Engl. Transl.); (United States), Journal Name: Sov. At. Energy (Engl. Transl.); (United States) Vol. 59:2; ISSN SATEA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ABSORPTION
B CODES
BARYON REACTIONS
BARYONS
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSS SECTIONS
ELEMENTARY PARTICLES
EPITHERMAL REACTORS
FAST REACTORS
FERMIONS
HADRON REACTIONS
HADRONS
KINETICS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON REACTIONS
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
ONE-GROUP THEORY
RADIATION FLUX
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
RESONANCE ABSORPTION
SCATTERING
SIMULATION
TARGETS
THERMAL REACTORS
THORIUM 232 TARGET
TOTAL CROSS SECTIONS
TRANSPORT THEORY
URANIUM 235 TARGET
URANIUM 238 TARGET