SIZZLE; one-dimensional multigroup diffusion depletion. [IBM360; FORTRAN IV]

Technical Report ·

OSTI ID:6423566

Blaine, R A

SIZZLE solves the one-dimensional, multigroup burnup problem in the diffusion theory approximation for fast intermediate reactors. After the initial calculation at t=0, average cross sections are computed for further calculations using one to six energy groups. Criticality may be maintained by use of a concentration search. The concentration of the various isotopes is permitted to vary only from region-to-region. Chains included are Th232, U238, and a fission product poison chain.IBM360; FORTRAN IV; OS/360.

• Research Organization: Atomics International, Canoga Park, CA (USA)
• OSTI ID: 6423566
• Report Number(s): ANL/NESC-58; ON: DE83048058
• Country of Publication: United States
• Language: English

Related Subjects

654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
A CODES
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
COMPUTER CODES
CRITICALITY
DIFFERENTIAL EQUATIONS
EQUATIONS
EVEN-EVEN NUCLEI
FISSION PRODUCTS
HEAVY NUCLEI
ISOTOPES
MATERIALS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
NUCLEI
ONE-DIMENSIONAL CALCULATIONS
RADIOACTIVE MATERIALS
RADIOISOTOPES
S CODES
THORIUM 232
THORIUM ISOTOPES
TRANSPORT THEORY
URANIUM 238
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES