Published 2011
| Version v1
Miscellaneous
Development of MCATHAS system of coupled neutronics/thermal-hydraulics in supercritical water reactor
Description
The MCATHAS system of coupled neutronics/Thermal-hydraulics in supercritical water reactor is described, which considers the mutual influence between the obvious axial and radial evolution of material temperature, water density and the relative power distribution. This system can obtain the main neutronics and thermal parameters along with burn-up. MCATHAS system is parallel processing coupling. The MCNP code is used for neutronics analysis with the continuous cross section library at any temperature calculated by interpolation algorithm; The sub-channel code ATHAS is for thermal-hydraulics analysis and the ORIGEN Code for burn-up calculation. We validate the code with the assembly of HPLWR and analyze the assembly SCLWR- H. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 978-1-926773-02-5
- Imprint Title
- ISSCWR-5. The 5th International Symposium on Supercritical-Water-Cooled Reactors
- Imprint Pagination
- 90.1 Megabytes
- Journal Page Range
- [9 p.]
Conference
- Title
- 5. International Symposium on Supercritical-Water-Cooled Reactors
- Dates
- 13-16 Mar 2011
- Place
- Vancouver, BC (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 48068440
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; COMPUTERIZED SIMULATION; MONTE CARLO METHOD; NEUTRON TRANSPORT; SUPERCRITICAL STATE; THERMAL HYDRAULICS; TURBULENT FLOW; WATER COOLED REACTORS
- Descriptors DEC
- CALCULATION METHODS; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTORS; SIMULATION
Optional Information
- Notes
- 10 refs., 3 tabs., 10 figs.