A progress update on selected AREVA NP advanced BWR methodologies
- 1. AREVA Inc, 2101 Horn Rapids Road, Richland, WA (United States)
- 2. AREVA GmbH, Paul-Gossen- Strasse 100, 91052 Erlangen (Germany)
- 3. Farawila et al Inc., Richland, WA (United States)
Description
This article presents an overview of select advances in AREVA NP methods concerning 3 topics: Analytical fuel rod model, Transient and accident simulation, and ATWSi post dryout treatment. Concerning the first topic, the analytical fuel rod model relies heavily on first-principles closed-form solutions instead of ever finer nodalization and higher dimensions of standard numerical methods such as finite differences or finite elements. This analytical fuel rod model takes full account of the complications that made numerical analysis necessary, e.g. variation of pellet thermal conductivity with temperature and burnup, and the radial dependence of fission power deposition in pellets. The model also calculates thermo-mechanical parameters such as clad stress and strain, fission gas release, pellet sintering and swelling, and pellet-clad gap size and thermal resistance. The model is suited for innovative fuel designs such as doped pellets. Concerning the second topic, the BWR evaluation model, AURORA-B, is an advanced transient and accident simulator including SRELAP5, a two fluid thermal hydraulic code comprehensively reviewed by international safety authorities for BWR and PWR applications; RODEX4, a best estimate fuel performance code used to evaluate the local thermal-mechanical behavior of fuel rods during postulated transients and accidents; and MB2-K, a neutron kinetics extension of the steady state core simulator MICROBURN-B2. The analytical domains will include transients as well as control rod drop and loss of coolant accidents. Extension of RODEX4 have been made to accommodate analysis of chromium-doped fuel. Concerning the third issue,The new AREVA post-dryout models can accurately predict dryout/re-wet followed by an ultimate failure to re-wet under oscillatory ATWSi (Anticipated Transient Without SCRAM with core instability) conditions. These models, while not a boiling curve based method, can qualitatively reproduce the characteristics of the boiling curve
Availability note (English)
Available from: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US), also available on CD-RomAdditional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 978-0-89448-734-7
- Imprint Title
- Top Fuel 2016 Proceedings
- Imprint Pagination
- 1670 p.
- Journal Page Range
- p. 77-86
Conference
- Title
- LWR fuels with enhanced safety and performance
- Acronym
- Top Fuel 2016
- Dates
- 11-15 Sep 2016
- Place
- Boise, ID (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 49101083
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATWS; BWR TYPE REACTORS; DOPED MATERIALS; DRYOUT; FUEL RODS; LOSS OF COOLANT; NUMERICAL ANALYSIS; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; THERMAL CONDUCTIVITY; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; MATERIALS; MATHEMATICS; MECHANICS; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 refs.