Detailed calculations in energy and space of effective neutron resonance cross sections

Journal Article · Fri Dec 01 04:00:00 EST 1978 · Nucl. Sci. Eng.; (United States)

OSTI ID:6309742

Aragones, J M

A method is developed for calculating effective neutron cross sections in the resolved resonance groups of homogeneous mixtures of cylindrical cells in regular reactor lattices. A rigorous treatment of the nucleonic and neutronic problems provides accurate numerical solutions with detailed dependence in energy and space for both Doppler-broadened cross sections and self-shielded neutron fluxes. The common simplifying approximations are not introduced, so that the method is used as a reference to analyze some of the detailed self-shielding effects that are commonly ignored or approximated in applications ranging from homogeneous mixtures of different resonant nuclides to cylindrical cells with nonuniform temperatures and concentrations within the fuel.

• Research Organization: Polytechnic Univ. of Madrid, Spain
• OSTI ID: 6309742
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 68:3; ISSN NSENA
• 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
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
CALCULATION METHODS
CROSS SECTIONS
ENERGY DEPENDENCE
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
HADRON REACTIONS
HEAVY NUCLEI
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MINUTES LIVING RADIOISOTOPES
NEUTRON REACTIONS
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
PLUTONIUM 239
PLUTONIUM 240
PLUTONIUM ISOTOPES
RADIOISOTOPES
REACTOR LATTICES
RESONANCE ABSORPTION
SPACE DEPENDENCE
URANIUM 235
URANIUM 238
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES