Published 2000
| Version v1
Report
Predicted and measured flow and temperature distributions in a facility for simulating in-reactor moderator circulation
- 1. Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)
- 2. Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)
Description
The Computational Fluid Dynamics code, MODTURC-CLAS, has been validated against experimental data obtained in the Moderator Test Facility at the Chalk River Laboratories of Atomic Energy of Canada Limited. The MTF is an integral scaled facility built to investigate moderator behaviour, having the key characteristics of a full-scale CANDU nuclear reactor calandria vessel. Predicted three-dimensional fluid flow and temperature distributions within the MTF vessel are in good agreement with the experimental data, which represent a range of operating conditions of the moderator in the recent CANDU 9 design. (author)
Availability note (English)
Available from Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- Report number
- AECL-CONF--00129
Conference
- Title
- 8. Annual conference of the CFD Society of Canada
- Dates
- 11-13 Jun 2000
- Place
- Montreal, Quebec (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 38037441
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; FLUID MECHANICS; MODERATORS; REACTOR CORES; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- HEAVY WATER MODERATED REACTORS; MECHANICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 2 refs., 4 figs.