Published September 1984
| Version v1
Report
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ASSERT-4 user's manual
Creators
- 1. Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.
- 2. Lakehead Univ., Thunder Bay, Ontario (Canada)
- 3. Rowe and Associates, Bellevue, WA (USA)
Description
ASSERT-4 is an advanced subchannel code being developed primarily to model single- and two-phase flow and heat transfer in horizontal rod bundles. This manual is intended to facilitate the application of this code to the analysis of flow in reactor fuel channels. It contains a brief description of the thermalhydraulic model and ASSERT-4 solution scheme, and other information required by users. This other information includes a detailed discussion of input data requirements, a sample problem and solution, and information describing how to access and run ASSERT-4 on the Chalk River computers
Availability note (English)
MF available from INIS under the Report Number.Files
17063212.pdf
Files
(1.3 MB)
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Additional details
Additional titles
- Subtitle (English)
- Two phase flow and heat transfer in rod bundles
Publishing Information
- Imprint Pagination
- 97 p.
- Report number
- AECL--8573
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 17063212
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- A CODES; COMPUTERIZED SIMULATION; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; MANUALS; TWO-PHASE FLOW
- Descriptors DEC
- COMPUTER CODES; DOCUMENT TYPES; ENERGY TRANSFER; FLUID FLOW; FUEL ASSEMBLIES; REACTOR CHANNELS; REACTOR COMPONENTS; SIMULATION
Optional Information
- Notes
- FORTRAN for CDC computers.