A Partition Decoupling Modeling and Overall Coupling Calculation Method for Sodium Cooled Fast Reactor Vessel

Abstract

The invention discloses a partition decoupling modeling and overall coupling calculation method of a sodium-cooled fast reactor vessel, which belongs to the technical field of nuclear reactor modeling and three-dimensional thermal fluid transient phenomenon algorithm, and specifically establishes a three-dimensional thermal fluid calculation model, Calculate the typical working conditions of the sodium-cooled fast reactor reactor vessel and internal components, simulate the three-dimensional thermal fluid transient phenomenon in the reactor vessel under the typical working conditions including normal operation, expected operation events and accidents, and obtain the normal operation and key The temperature field and flow field distribution characteristics of key structures and components in the reactor under accident conditions, and its three-dimensional thermal distribution and change characteristics are clarified. The three-dimensional thermal parameters obtained based on numerical simulation calculations can provide support and basis for stress assessment of sodium-cooled fast reactor-related structures, and also provide technical reference for numerical simulation of various models with large differences in flow channel size and complex structures.

Description

technical field [0001] The invention belongs to the technical field of nuclear reactor modeling and three-dimensional thermal fluid transient phenomenon algorithm; in particular, it relates to a partition decoupling modeling and overall coupling calculation method of a sodium-cooled fast reactor vessel, and specifically relates to the three-dimensional modeling of complex models with huge differences in structural dimensions Thermal fluid calculations. Background technique [0002] Sodium-cooled fast reactor (SFR for short) is the reactor type with the most mature technology and the richest operating experience among the six fourth-generation reactors. In fast reactors, the flow of coolant sodium is relatively complicated. Taking China Experimental Fast Reactor (CEFR) as an example, the primary circuit of CEFR adopts a pool structure. The core and primary circuit equipment are all in the main container, and liquid metal sodium is used as the primary circuit. Coolant and sec...

AI Technical Summary

Problems solved by technology

However, due to the complexity of the pool-type fast reactor structure and circuit layout, the size of the reactor structure varies greatly. The overall height of the reactor vessel is 15m, and the flow channel of the pump cooling system is only 70mm, a difference of 214 times, making grid division difficult.

Domestic scholars have carried out numerical simulations on individual component structures in sodium-cooled fast reactors, but there has not been a similar precedent for transient numerical simulations of the whole reactor. Flow Field Distribution Characteristics for Stress Assessment of Sodium Cooled Fast Reactor Related Structures

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