Modeling and calculation method for flow channel of main pump of fast reactor based on virtual valve

Abstract

The invention discloses a modeling and calculation method for a flow channel of a main pump of a fast reactor based on a virtual valve and belongs to the technical field of three-dimensional numericalsimulation of a reactor. The method comprises the steps of based on a pool-type sodium-cooled fast reactor, reasonably simplifying a reactor vessel and reactor internals to establish a three-dimensional pool-type fast reactor model; performing three-dimensional thermo-technical fluid transient calculation under multiple working conditions by use of a model; and performing part of simple change onsurface attributes of a connection coupling module of a primary main pump by changing the attribute of each surface of the connection coupling module between the main pump and a pressure pipe. The instantaneous conditions of the in-pile flowing process can be accurately simulated, the analysis of a primary loop accident system of the fast reactor and the three-dimensional thermo-technical transient calculation are performed under various types of working conditions, including normal operation, expected operating events and accident working conditions. With the modeling and calculation methodfor the flow channel of the main pump of the fast reactor based on the virtual valve disclosed by the invention, the workload of modeling and calculation is greatly reduced; the effect that the calculation of multiple working conditions can be completed by use of a set of grid files is implemented and the support and basis are provided for design and safety analysis of the fast reactor.

Description

technical field [0001] The invention belongs to the technical field of three-dimensional numerical simulation of fast reactors, and in particular relates to a modeling and calculation method of a main pump circulation channel of a fast reactor based on a "virtual valve". Specifically, it is a method that can be used for system analysis of fast reactor primary circuit accidents and 3D thermal transient calculation of fluid in the reactor under various operating conditions, including normal operation, expected operating events and accident conditions. Background technique [0002] Fast reactors are an important direction of the fourth generation reactors. Fast reactors can consume the nuclear waste produced by thermal neutron reactors, use the non-fissile nuclides that exist widely in nature that thermal neutron reactors cannot use, and generate heat energy. Taking the pool-type sodium-cooled fast reactor as an example, the system includes primary and secondary sodium loops an...

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Problems solved by technology

For the coupling simulation of the whole pool fast reactor, A.Toti et al. used RELAP5 and FLUENT to conduct three-dimensional calculations in the transient state of water loss for the research reactor MYRRHA. U.Parthasarathy et al. used commercial software and two-loop one-dimensional software Combined method to calculate the effect of the waste heat removal system of the PHENIX reactor, Xu Yijun and others modeled the cold and hot sodium pools of CEFR and performed calculations under transient conditions, but the model is relatively simplified and cannot be accurately calculated Simulate the flow characteristics of the fluid in the reactor under various working conditions

At present, there is no precedent for full-stack and detailed three-dimensional transient numerical simulation of fast reactors at home and abroad.

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