BURNUP OF FUEL IN WATER-MODERATED WATER-COOLED POWER REACTORS AND URANIUM- WATER LATTICE EXPERIMENTS

Technical Report · Sat Oct 31 04:00:00 EST 1959

OSTI ID:4262372

Feinberg, S M; Antsiferov, E S

The method and the results are reported of numerical calculations of fuel burning in ordinary water-cooled and -moderated reactors with a homogeneous core which use fresh slightly enriched fuel. The point of departure of the method is the notion of stationary conditions at which the process is maintained in the reactor as a result of a regular replacement of the burned-out fuel by fresh fuel. The results of the calculations allow a conclusion to be drawn regarding the dependence of the fuel life and the isotopic composition of the discharged material on such factors as the percentage of enrichment of the fresh fuel, the water--uranium volume ratio, the dimensions of tbe core, and the frequency of fuel reloading. A study is made of the dependence of the fuel life and irregular heat production in the - reactor on the trajectory of motion of the buming fuel in the core. The theory of a uranium--water reactor is proposed, which is formed by a periodic structure of greatly or slightly enriched zones. The results are given of experimentally studying the physical parameters of a unanium--water lattice. Slugs of natural and enriched uranium were investigated. The material parameter of the lattice was determined from measurements of neutron distribution. A new interpretation is discussed of the multiplication fuctor and of its components, suitable for a reactor with a hand spectrum of neutrons. Various parameters of the lattice are dealt with from this viewpoint. (auth)

• Research Organization: U.S.S.R.
• NSA Number: NSA-13-007275
• OSTI ID: 4262372
• Report Number(s): A/CONF.15/P/2145
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BUCKLING
BURNUP
CONFIGURATION
CRITICALITY
DENSITY
DISTRIBUTION
EFFICIENCY
ENRICHMENT
EPITHERMAL NEUTRONS
EQUATIONS
FAST FISSION FACTOR
FISSION PRODUCTS
FUEL ELEMENTS
FUELS
HEAT TRANSFER
HOMOGENEOUS REACTORS
IRRADIATION
ISOTOPES
MASS
MATERIALS TESTING
MEASURED VALUES
MULTIPLICATION FACTORS
NATURAL URANIUM FUEL
NEUTRON FLUX
NUMERICALS
POISONING
POWER PLANTS
PRODUCTION
REACTIVITY
REACTOR CORE
REACTOR FUELING
REACTORS
RESONANCE ESCAPE PROBABILITY
RODS
SPECTRA
STABILITY
THERMAL FISSION FACTOR
THERMAL UTILIZATION
URANIUM
USSR
VARIATIONS
VOLUME
WATER COOLANT
WATER MODERATOR
ZONES