Published 1990 | Version v1
Miscellaneous Metadata-only

Application of local-parameter lattice properties to fuel management simulations in Ontario Hydro reactors

Creators

  • 1. Ontario Hydro, Toronto, ON (Canada)
  • 2. Atomic Energy of Canada Ltd., Sheridan Park, ON (Canada). CANDU Operations

Description

A refinement to the Ontario Hydro fuel management code SORO allows local values, instead of reactor-averaged global values, of coolant density, fuel temperature, and bundle power (flux) to be used when evaluating lattice properties. The fuel temperature/flux component of this refinement was assessed by comparing local parameter and global parameter simulations of Bruce B reactor operating histories (both past and future). Local parameter re-simulations of past histories do not significantly improve fits to measurements; i.e., instrumented channel powers, channel outlet temperatures, and in-core detector fluxes. However, self-consistent long-term (four year) pre-simulations of future histories show typical reductions of 5% in maximum bundle power, 1% in maximum channel power, and i% in channel power peaking factor, which imply substantial potential economic benefits for Ontario Hydro. (Author) 4 refs., 4 tabs., 2 figs

Part of:
Proceedings of the 11th Annual Conference of the Canadian Nuclear Society

Additional details

Publishing Information

Imprint Title
Proceedings of the 11th Annual Conference of the Canadian Nuclear Society
Imprint Pagination
440 p.
Journal Page Range
p. 3.1-3.5.
Report number
INIS-mf--13847

Conference

Title
Canadian Nuclear Society 11. annual conference.
Dates
3-6 Jun 1990.
Place
Toronto, ON (Canada).

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
25031751
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BRUCE-5 REACTOR; FUEL ELEMENTS; FUEL MANAGEMENT; PRIMARY COOLANT CIRCUITS; REACTOR LATTICE PARAMETERS; S CODES; TEMPERATURE DISTRIBUTION
Descriptors DEC
CANDU TYPE REACTORS; COMPUTER CODES; COOLING SYSTEMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MANAGEMENT; NATURAL URANIUM REACTORS; NUCLEAR MATERIALS MANAGEMENT; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS

Optional Information