LATTICE PARAMETER MEASUREMENTS IN ZED-2

Technical Report · Mon Jul 15 04:00:00 EDT 1963

OSTI ID:4629280

Green, R E; Bigham, C B

Experiments were performed in the ZED-2 reactor to determine lattice parameters for fuel assemblies which closely resemble the fuel channels of the CANDU power reactor. The experimental fuel consisted of 19-rod clusters of 1.421 cm diameter, Zircaloy-clad UO/sub 2/ of density 10.4 approximates gm/cm/sup 3/ housed in double-walled tube assemblies to simulate the pressure and calandria tubes of the power reactor. Measurements were made in hexagonal lattices for several pitches in the range 18 to 36 cm with three different materials filling the coolant spaces of the fuel assemblies; viz., D/sub 2/O, air (i.e. void) and an organic liquid called HB-40, which has the chemical formula C/sub 18/H/sub 22.0/. The moderator was in all cases D/sub 2/O. The following quantities were determined: bucklings that were derived from macroscopic flux distributions and reactivity measurements, microscopic neutron activation distributions from which the average neutron densities in the various cell materials were deduced, the epithermal neutron spectrum index, the effective neutron temperature, fast fission ratios, and initial conversion ratios. (auth)

• Research Organization: Atomic Energy of Canada, Ltd., Chalk River, Ontario (Canada)
• NSA Number: NSA-17-038564
• OSTI ID: 4629280
• Report Number(s): AECL-1814; CONF-133-3
• Country of Publication: Canada
• Language: English

Related Subjects

ACTIVATION
AIR
BUCKLING
CANDU
CONVERSION
CRITICAL ASSEMBLIES
DENSITY
EPITHERMAL NEUTRONS
FUEL CANS
FUEL ELEMENTS
HEAVY WATER COOLANT
HEAVY WATER MODERATOR
JACKETS
MEASURED VALUES
MULTIPLICATION FACTORS
NEUTRON FLUX
NEUTRONS
ORGANIC COOLANT
REACTIVITY
REACTOR FUELING
REACTOR TECHNOLOGY
RESEARCH REACTORS
SPECTRA
TEMPERATURE
TUBES
URANIUM DIOXIDE
ZED-2
ZIRCALOY