MEASUREMENT OF REACTOR PARAMETERS. PART II

Journal Article · Sun Jan 01 04:00:00 EST 1961 · Energia es Atomtech.

OSTI ID:4049206

Bata, L

BS>Calculation of the thermal utilization factor is relatively simple in the case of homoganeous systems because the cross section is not dependent on the location as the number of fissionable and moderating nuclei remains constant throughout the core. In heterogeneous systems the average flux must be calculated or measured in various points of the fuel and of the moderator; both integral and differential methods of flux distribution measurement may be used. U-235 foils were successfully used as detectors. While the thermal utilization may be estimated with good approximation on the basis of a differential method, it is not quite acceptable for determining the flux distribution The diffusion equation must he corrected for the following reasons: transient phenomena may occur at the fuel moderator interface; the fission neutrons are not completely thermal and monoenergetic; the neutron temperature may exceed the moderator temperature. The flux distribution of the subcritical assembly SR-1 formed by the fuel elements of the VVRSz reactor was determined using Rh foils. (TTT)

• Research Organization: Central Physics Research Inst.
• NSA Number: NSA-15-015224
• OSTI ID: 4049206
• Journal Information: Energia es Atomtech., Journal Name: Energia es Atomtech. Vol. Vol: 14
• Country of Publication: Country unknown/Code not available
• Language: Hungarian

Related Subjects

CRITICAL ASSEMBLIES
CROSS SECTIONS
DETECTION
DIFFUSION
DISTRIBUTION
FISSION
FOILS
HOMOGENEOUS REACTORS
MEASURED VALUES
MODERATORS
NEUTRON FLUX
NEUTRONS
REACTOR TECHNOLOGY
REACTORS
RHODIUM
SLOWDOWN
THERMAL UTILIZATION
TRANSIENTS
TRANSPORT THEORY
URANIUM 235