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Title: EXPERIMENTAL PARAMETERS FOR NPD AND CANDU TYPE FUEL ELEMENTS IN D$sub 2$O

Technical Report ·
OSTI ID:4705445

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