Capabilities of Reynolds stress turbulence model in applications to thermal stratification
Creators
- 1. Argonne National Lab., IL (United States). Energy Technology Div.
Description
In the safety analysis of advanced fast breeder reactors, licensing authorities require that inherent safety capabilities be proved by numerical simulation with well-validated computer programs. Even in the worst case of loss of power to the primary pumps, natural convection circulation must provide, through intermediate heat exchangers, a heat sink sufficient to prevent coolant temperatures from reaching saturation and triggering development of a two-phase flow domain with subsequent reduction of coolant capabilities and loss of core integrity. Numerical simulations of reactor coolant behavior require the modeling of turbulent flows in the critical transition phase between forced and natural convection. Also required is the modeling of impact of coolant temperature stratification on turbulence, which can be enhanced or suppressed according to unstable or stable stratification patterns. Therefore the accuracy of computer codes depends on the mathematical modeling, particularly on the modeling of turbulence in thermal stratification. A Reynolds stress turbulence model (RSM) has been implemented in the COMMIX code, together with transport equations describing turbulent heat fluxes, variance of temperature fluctuations, and dissipation of turbulence kinetic energy. This article outlines the model, explains the verifications performed thus far, and discusses potential applications of the RSM in the analysis of thermal stratification in engineering systems. The problem of analyzing thermal stratification and minimizing the impact of thermal stresses on structures is of concern in both nuclear and conventional industries
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1193-X
- Imprint Title
- Transient thermal hydraulics, heat transfer, fluid-structure interaction, and structural dynamics. PVP-Vol. 270
- Imprint Pagination
- 165 p.
- Journal Page Range
- p. 11-22.
Conference
- Title
- 1994 pressure vessels and piping conference.
- Dates
- 19-23 Jun 1994.
- Place
- Minneapolis, MN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26030526
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- C CODES; COOLANTS; FINITE DIFFERENCE METHOD; FLOW MODELS; HEAT TRANSFER; LMFBR TYPE REACTORS; NATURAL CONVECTION; NUCLEAR POWER PLANTS; SAFETY ANALYSIS; SHEAR; STRATIFICATION; TEMPERATURE GRADIENTS; THEORETICAL DATA; TURBULENT FLOW; USES; VERIFICATION
- Descriptors DEC
- BREEDER REACTORS; CALCULATION METHODS; COMPUTER CODES; CONVECTION; DATA; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; INFORMATION; ITERATIVE METHODS; LIQUID METAL COOLED REACTORS; MATHEMATICAL MODELS; NUCLEAR FACILITIES; NUMERICAL DATA; NUMERICAL SOLUTION; POWER PLANTS; REACTORS; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- CONF-940613--.