Numerical simulation on coolant flow and heat transfer in core
Creators
- 1. Tsinghua Univ., Beijing (China). Dept. of Engineering Mechanics
Description
To simulate the coolant flow and the heat transfer characteristics of a core, a computer code, THAPMA (Thermal Hydraulic Analysis Porous Medium Analysis) has been developed. In THAPMA code, conservation equations are based on a porous-medium formulation, which uses four parameters, i.e, volume porosity, directional surface porosity, distributed resistance, and distributed heat source (sink), to model the effects of fuel rods and other internal solid structures on flow and heat transfer. Because the scheme and the solution are very important in accuracy and speed of calculation, a new difference scheme (WSUC) has been used in the energy equation, and a modified PISO solution method have been employed to simulate the steady/transient states. The code has been proved reliable and can effectively solve the transient state problem by several numerical tests. According to the design of Qinshan NPP-II, the flow and heat transfer phenomena in reactor core have been numerically simulated. The distributions of the velocity and the temperature can provide a theoretical basis for core design and safety analysis
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 18
- Journal Issue
- 4
- Journal Page Range
- p. 332-339.
- ISSN
- 0258-0926
- CODEN
- HDGOE6
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 28076049
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLUID FLOW; HEAT TRANSFER; HYDRAULICS; NUMERICAL SOLUTION; PWR TYPE REACTORS; REACTOR CORES; STEADY-STATE CONDITIONS; T CODES; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS