Published 1997
| Version v1
Miscellaneous
Dynoboss: a computer code for the nonlinear dynamics of boiling water nuclear reactors
Creators
- 1. Instituto de estudos Avancados (Brazil)
- 2. Rensselaer Polytechnic Institute, New York (United States)
Description
The DYNOBOSS code can be used for the analysis of instabilities in boiling systems in general and BWR in particular. The DYNOBOSS code combines models BWR thermal-hydraulics and neutronics. The thermal-hydraulics model includes a multi-parallel channel core model and models of other major components of the BWR recirculation loop. The modeling of two-phase flows utilizes the drift-flux formulation and include such important factors as subcooled boiling, heated wall dynamics and others. The steady-state operating conditions are obtained coupling the loop thermal-hydraulics with a two-dimensional model of core neutronics. The results have showed that the DYNOBOSS code properly predicts the onset and propagation of unstable oscillations in BWR
Additional details
Publishing Information
- Imprint Title
- Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety
- Imprint Pagination
- 1493 p.
- Journal Page Range
- p. HH3.1-HH3.6
Conference
- Title
- 5. international topical meeting on nuclear thermal hydraulics, operations and safety
- Dates
- 14-18 Apr 1997
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 29048962
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; D CODES; EXPERIMENTAL DATA; HEAT TRANSFER; HYDRAULICS; INSTABILITY; MATHEMATICAL MODELS; NONLINEAR PROBLEMS; NUCLEAR POWER PLANTS; NUMERICAL SOLUTION; OSCILLATION MODES; REACTOR CORES; TWO-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW
- Descriptors DEC
- COMPUTER CODES; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; INFORMATION; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS