EXPERIMENTAL PARAMETERS FOR NPD AND CANDU TYPE FUEL ELEMENTS IN D$sub 2$O
Experiments carried out in the ZED-2 reactor to determine lattice parameters for fuel assemblies which are similar to the fuel channels of the NPD and CANDU power reactors are described. Bucklings were determined from macroscopic neutron fiux distribution and reactivity measurements. Microscopic neutron fiux distribution measurements were made in central lattice cells and the results combined with measurements of the Westcott epithermal neutron spectrum parameter (r) and effective neutron temperatures to determine the thermal utilization (f), and the thermal diffusion area (L/sup 2/). Fast fission ratios and initial conversion ratios were also measured from which values of the fast fission factor ( epsilon ) and the resonance escape probability (p), respectively, were deduced. Measurements were made at various fuel assembly spacings in the range 18 to 36 cm in hexagonal lattices. The experimental results were compared with calculated parameters obtained from the latest version of the Chalk River lattice calculation program. (auth)
- Research Organization:
- Atomic Energy of Canada Ltd. Chalk River Project, Chalk River, Ont.
- NSA Number:
- NSA-17-011939
- OSTI ID:
- 4705445
- Report Number(s):
- CRL-75; AECL-1640
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- Canada
- Language:
- English
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Related Subjects
BREEDING
BUCKLING
CANADA
CANDU
CHALK RIVER
COMPUTERS
CONFIGURATION
CRITICALITY
DIFFUSION LENGTH
DISTRIBUTION
EPITHERMAL NEUTRONS
EQUATIONS
FAST FISSION FACTOR
FAST NEUTRONS
FISSION
FUEL ELEMENTS
HEAVY WATER MODERATOR
HYDROLOGY
LATTICES
MEASURED VALUES
MULTIPLICATION FACTORS
NEUTRON FLUX
NPD
NPD-2
NUMERICALS
POWER PLANTS
PROGRAMMING
QUANTITATIVE ANALYSIS
REACTIVITY
REACTOR CORE
REACTORS
RESEARCH REACTORS
RESONANCE ESCAPE PROBABILITY
RIVERS
SPECTRA
TEMPERATURE
THERMAL NEUTRONS
THERMAL UTILIZATION
USES
ZED-2
ZONES