Summary of researches on operational characteristics and safety of molten salt fast reactors based on neutronics and thermal-hydraulics coupling analysis

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Hiroyasu Mochizuki
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引用次数: 0

Abstract

The present paper mainly summarizes the operational and safety characteristics found by the neutronics and thermal-hydraulics coupling analysis for molten-salt fast reactors (MFR). Analysis methods for MFRs have been developed using system codes and Computational Fluid Dynamics (CFD) codes. Traditionally, the analysis has been limited to single-phase flow of the molten fuel salt, but recently analysis has been conducted under two-phase flow conditions with a small amount of helium gas injected to remove fission products (FP). In the MSFR developed by the EU, the void fraction due to two-phase flow is locally distributed, and a method for analyzing this by coupling advanced neutronics calculation methods with a CFD code has been proposed. On the other hand, a method that models all heat transport systems using a system code with reactor point kinetic (PRK) models have also been proposed. In this case, a CFD code is also used to calculate the precise behavior of flow scheme in the reactor. Since MFRs generally do not have control rods, the method of starting up the reactor must be different from that of light water reactors (LWR). Various methods have been proposed, but this paper introduces a startup method that takes advantage of the characteristics of two-phase flow and its negative reactivity. In the analysis of load-following operation, several methods have been proposed to perform time-order load-following operation by actively varying the reactor power, as in conventional LWRs. Recently, a passive load-following operation method has been proposed that fully exploits the characteristics of MFR. In this passive method, the reactor is operated to respond naturally to temperature changes in the heat transport system caused by flow rate changes corresponding to load variations in the energy conversion system, without controlling the fuel and intermediate circuits. This operation method introduces a heat storage tank in the intermediate circuit, which allows load-following operation in all modes from long to short duration. With regard to safety, the paper presents examples of system code and CFD code analysis of the behavior with a safety protection system bypassed for various transients in two-phase flow conditions. These analyses show that molten salt fast reactors always transition to the safe operating range after transients.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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