Conceptual Design and Evaluation of Residual Heat Removal System for Small Lead-Bismuth Fast Reactor

2021 ◽  
Author(s):  
Shijia Xu ◽  
Qinglong Wen ◽  
Shenhui Ruan ◽  
Ningning Zhao ◽  
Yukang Liu
Keyword(s):  
Mass Flow Rate ◽  
Conceptual Design ◽  
Mass Flow ◽  
Flow Rate ◽  
Fast Reactor ◽  
Heat Removal ◽  
The Core ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Abstract A high efficient and reliable residual heat removal system (RHRS), which is of great importance in the development of Lead-Bismuth Cooled Fast Reactor (LBFR), was conceptually designed in present study. Based on the design of the RHRS and LBFR, the RELAP5 4.0 code is used to model the system, and then the numerical calculation of steady and transient state was carried out to obtain the important thermal-hydraulic characteristic parameters. Meanwhile, the variations of the parameters were obtained during the transient process, such as the fuel cladding temperature and the natural circulation mass flow rate. The results show that the mass flow rate of the core finally stabilizes at 3.9 kg/s, which is about 1.35% of the rated flow. The peak cladding temperature is less than 750.3 K within 72 h during the whole process, which is far below the temperature safety limit. Therefore, it can be considered that the RHRS can successfully remove the core decay heat of LBFR. This research lays a solid technical foundation for the conceptual design of the RHRS.

The Application of Heat Pipe Discharge Containment Heat Experimental Study: New Type of Passive Containment Heat Removal System Concept Design

2017 ◽  
Author(s):  
Haiqi Qin ◽  
Daogang Lu ◽  
Shengfei Wang
Keyword(s):  
Conceptual Design ◽  
Nuclear Power ◽  
Large Scale ◽  
Heat Removal ◽  
Operating Conditions ◽  
Concept Design ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Practice has proved that nuclear power technology development and operation of nuclear power is a clean, safe and large-scale provided stable power. AP1000 uses a large number of passive safety technologies. Passive residual heat removal system is an important part, in the long-term cooling stage of nuclear reactor normal operating conditions or accident conditions, to prevent the core meltdown. The research of this paper is to solve the long-term discharge of residual heat of the containment in the accident condition of nuclear power plant. Based on the passive heat removal system of AP1000, combined with the heat transfer characteristics and advantages of heat pipes, the PRHR system is further improved on the basis of the present situation, and a conceptual design of passive containment residual heat removal system is proposed. In order to further verify the feasibility of the conceptual design, we make a simplified simulation of small containment test bench to carry out experimental verification and give a detailed experimental design.

scholarly journals CFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor

2018 ◽  
Vol 2018 ◽  
pp. 1-11
Author(s):  
Jiarun Mao ◽  
Lei Song ◽  
Yuhao Liu ◽  
Jiming Lin ◽  
Shanfang Huang ◽  
...  
Keyword(s):  
Heat Exchange ◽  
Fast Reactor ◽  
Natural Circulation ◽  
Heat Removal ◽  
Engineering Project ◽  
Decay Heat ◽  
The Core ◽  
Main Vessel ◽  
Heat Removal System ◽  
Removal System

This paper presents capacity of the passive decay heat removal system (DHRS) operated under the natural circulation conditions to remove decay heat inside the main vessel of the Lead-bismuth eutectic cooled Fast Reactor (LFR). The motivation of this research is to improve the inherent safety of the LFR based on the China Accelerator Driven System (ADS) engineering project. Usually the plant is damaged due to the failure of the main pumps and the main heat exchangers under the Station Blackout (SBO). To prevent this accident, we proposed the DHRS based on the diathermic oil cooling for the LFR. The behavior of the DHRS and the plant was simulated using the CFD code STAR CCM+ using LFR with DHRS. The purpose of this analysis is to evaluate the heat exchange capacity of the DHRS and is to provide the reference for structural improvement and experimental design. The results show that the stable natural circulations are established in both the main vessel and the DHRS. During the decay process, the heat exchange power is above the core decay heat power. In addition, in-core decay heat and heat storage inside the main vessel are efficiently removed. All the thermal-hydraulics parameters are within a safe range. Moreover, the highest temperature occurs at the upper surface of the core. A swirl occurs at the corner of the lateral core surface and some improvements should be considered. And the natural circulation driving force can be further increased by reducing the loop resistance or increasing the natural circulation height based on the present design scenario to enhance the heat exchange effect.

Experimental Research on Characteristics of Passive Residual Heat Removal System for Small Modular Reactors Under the Station Blackout Accident

2016 ◽  
Author(s):  
Xiaodong Lu ◽  
Chuanxin Peng ◽  
Yan Zhang ◽  
Xuesong Bai ◽  
Yuanfeng Zan ◽  
...  
Keyword(s):  
Experimental Research ◽  
Heat Removal ◽  
Injection System ◽  
Primary System ◽  
Water Tank ◽  
The Core ◽  
Station Blackout ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

An experimental research on performance characteristics of passive residual heat removal system (PRHRS) for the small modular reactor designed by Nuclear Power Institute of China (NPIC) under the station blackout accident was performed in the CREAS facility, which consists of the primary system, the secondary system, the passive safety injection system, the passive residual heat removal system, the overpressure protection system and the auxiliary system. The experimental results show that, after the station blackout accident, a stable two-phase natural circulation between the steam generators and the heat exchanger in the PRHRS was established with a mass flow of 0.4T/h, thus the heat from the primary system was removed to the water in the containment water tank (CWT). During this period, the core decay residual heat and the sensible heat were removed from the primary system by the PRHRS effectively. The cold water from the core makeup tanks was injected into the reactor pressure vessel for core cooling. The peaked primary pressure was 16.3MPa and less than relief valve opening pressure 16.9MPa. In addition, the average coolant temperature of the reactor core reduced below 483 K, and the reactor operated safely.

scholarly journals Analysis on passive residual heat removal system with heat pipes for longterm decay heat removal of small lead-based reactor

2021 ◽  
Vol 236 ◽  
pp. 01018
Author(s):  
Chongju Hu ◽  
Wangli Huang ◽  
Zhizhong Jiang ◽  
Qunying Huang ◽  
Yunqing Bai ◽  
...  
Keyword(s):  
Three Dimensional ◽  
Heat Removal ◽  
Heat Pipes ◽  
Decay Heat ◽  
The Core ◽  
Accident Condition ◽  
Computational Fluid Dynamics Cfd ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

.A lead-based reactor with employing heat pipes as passive residual heat removal system (PRHRS) for longterm decay heat removal was designed. Three-dimensional computational fluid dynamics (CFD) software FLUENT was adopted to simulate the thermal-hydraulic characteristics of the PRHRS under Station-Black-Out (SBO) accident condition. The results showed that heat in the core could be removed smoothly by the PRHRS, and the core temperature difference is less than 20 K.

Design and performance analysis of passive residual heat removal system for a lead-cooled fast reactor

2018 ◽  
Vol 103 ◽  
pp. 236-242
Author(s):  
Guowei Wu ◽  
Yazhou Li ◽  
Minghuang Wang ◽  
Yuan Chen ◽  
Lizhi Wang
Keyword(s):  
Performance Analysis ◽  
Fast Reactor ◽  
Heat Removal ◽  
And Performance ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Thermal-Hydraulic Character Effect Factors Analysis for Passive Residual Heat Removal System of Sodium-Cooled Fast Reactor

2012 ◽  
Author(s):  
Xiaolong Sun ◽  
Minjun Peng ◽  
Genglei Xia
Keyword(s):  
Heat Exchanger ◽  
Fast Reactor ◽  
Heat Exchangers ◽  
Heat Removal ◽  
Factors Analysis ◽  
Higher Temperature ◽  
Heat Removal System ◽  
China Experimental Fast Reactor ◽  
Removal System ◽  
Residual Heat

A theoretical investigation was performed on the passive residual heat removal system (PRHRs) of China Experimental Fast Reactor (CEFR). The system contained two air heat exchangers, two independent heat exchangers and several pipes. By means of JTOPMERET code developed by GSE, the thermodynamic model of the system had been built. Based on the model, transient characteristics of the PRHRs have been discussed in detail. Through the calculation analysis, it is then indicated that the capacity of removing residual heat was affected by some factors. The faster speed of air in the air heat exchanger, the higher temperature and the larger heat transfer area of the air heat exchanger are favorable to the PRHRs. At the same time, the calculated parameters variation trends are reasonable according to the Experimental data from CEFR.

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