Steady State Modelling and Validation of Once Through Steam Generator
- 1. Reactor Design Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
Description
One dimensional steady state model is developed for straight vertical once through counter current shell and tube steam generator for PFBR with water flowing through tubes and sodium through shell. All the heat transfer processes i.e. preheating, evaporation of water and superheating of the steam happen along the length of the tube. The length of the steam generator is divided into a number of control volumes. For modelling water side, continuity, momentum and energy equations are solved for single phase water, two phase steam and super heated vapour over the length of the tube using homogeneous model. The density variation of sodium is not considered and only energy equation is solved for sodium. The differential equations are discretised to linear algebraic equations using finite difference scheme. All three terms advection, frictional and gravitational are considered in momentum equation of water, while only advection and source term are considered in energy equation of water and sodium. The linear algebraic equations are then solved simultaneously using iterative method to get the temperature and pressure profiles in the tube and shell side. Water side heat transfer coefficient is calculated using Steiner and Taborek asymptotic model and Subbotin correlation is used for sodium side heat transfer coefficient. The code developed can be applied to simulate similar steam generators of any length with any number of tubes. Towards validation of the mathematical model and the solution method, 19 tube steam generator tested in in-house steam generator test facility (SGTF) has been simulated and the predicted results are compared with the measured data. Results from the code match well with experimentally observed data from the facility. In addition, grid sensitivity studies have been carried out to establish consistency in the solution. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-108618-1
- Imprint Title
- Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Proceedings of an International Conference. Companion CD-ROM
- Imprint Pagination
- [1 CD-ROM]
- Series
- Proceedings Series
- Journal Page Range
- 9 p.
- ISSN
- 0074-1884
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51006209
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADVECTION; ASYMPTOTIC SOLUTIONS; COMPUTERIZED SIMULATION; COUNTER CURRENT; DIFFERENTIAL EQUATIONS; EVAPORATION; HEAT TRANSFER; MATHEMATICAL MODELS; ONE-DIMENSIONAL CALCULATIONS; SENSITIVITY ANALYSIS; SODIUM; STEADY-STATE CONDITIONS; STEAM; STEAM GENERATORS; SUPERHEATING; TEST FACILITIES; TUBES; VALIDATION; VAPORS; WATER
- Descriptors DEC
- ALKALI METALS; BOILERS; ELEMENTS; ENERGY TRANSFER; EQUATIONS; FLUIDS; GASES; HEATING; HYDROGEN COMPOUNDS; MASS TRANSFER; MATHEMATICAL SOLUTIONS; METALS; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; SIMULATION; TESTING; VAPOR GENERATORS
Optional Information
- Notes
- 6 refs., 6 figs., 1 tab. Imprint:refs., figs., tabs.
- Secondary number(s)
- IAEA-CN--245-332