Test of dissolution of simulated corrosion-oxides in primary loop of the AP1000 reactor

2020 ◽  
Vol 326 (2) ◽  
pp. 1151-1158
Author(s):  
Yu-jie Cui ◽  
Ming-liang Wu ◽  
Wei Zhao ◽  
Yong-xian Wang ◽  
Li-xiao Guo ◽  
...  
Keyword(s):  
Primary Loop ◽  
Ap1000 Reactor

AP1000 Nuclear Reactor and Primary Loop Modeling Based on Relap5-3D and 3Keymaster Simulation Platform

2012 ◽  
Vol 214 ◽  
pp. 510-514 ◽  
Author(s):  
Hui Ming Wei ◽  
Xuan Zhang ◽  
Tai Li Liu
Keyword(s):  
Nuclear Reactor ◽  
Reactor Core ◽  
System Model ◽  
Simulation Platform ◽  
Loop Modeling ◽  
Simulation Code ◽  
Primary Loop ◽  
Steam Generator Model ◽  
Ap1000 Reactor ◽  
Coolant System

In this paper, the advanced 3Keymaster simulation platform and RELAP5 simulation code are introduced. At the same time, the AP1000 nuclear reactor and primary loop modeling method is discussed in detail based on Remlap 5 and 3Keymaster simulation platform. The typical Relap5 nasalization cells of AP1000 nuclear reactor and primary loop system are showed in Fig.1. The Fig.2 shows the AP1000 reactor coolant system model. Fig.3 shows the AP1000 reactor core and pressure vessel model. Fig.4 shows the AP1000 nuclear reactor steam generator model.

The effects of thermal stress on the crack propagation in AP1000 reactor pressure vessel

2020 ◽  
Vol 110 ◽  
pp. 102798
Author(s):  
KaiTai Liu ◽  
Mei Huang ◽  
JunJie Lin ◽  
HaiPeng Jiang ◽  
BoXue Wang ◽  
...  
Keyword(s):  
Thermal Stress ◽  
Crack Propagation ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Ap1000 Reactor ◽  
Reactor Pressure

scholarly journals Accident Analyses of Optimal Designed Primary Loop

2020 ◽  
Vol 565 ◽  
pp. 012098
Author(s):  
Lei Chen ◽  
Feifei Song ◽  
Zhen Jia
Keyword(s):  
Primary Loop

An analysis of gas leaks from sodium into the gas cushions of a BR-10 primary loop

1991 ◽  
Vol 70 (1) ◽  
pp. 42-47
Author(s):  
I. A. Efimov ◽  
L. I. Mamaev ◽  
V. A. Marchenko ◽  
V. S. Filonov
Keyword(s):  
Primary Loop ◽  
Gas Leaks

Study on NC in primary loop and reverse flow in SG during SBO combining with SBLOCA

2021 ◽  
Vol 141 ◽  
pp. 103983
Author(s):  
Mingrui Li ◽  
Jianli Hao ◽  
Wenzhen Chen ◽  
Xi Chu
Keyword(s):  
Reverse Flow ◽  
Primary Loop

Simulations of the dust behavior in the sampling and dust filters in the primary loop of HTR-10

2018 ◽  
Vol 340 ◽  
pp. 112-121 ◽  
Author(s):  
Wei Peng ◽  
Qi Sun ◽  
Feng Xie ◽  
Yueyuan Jiang
Keyword(s):  
Primary Loop

scholarly journals Design of the Online Gross γ Monitoring Instrument at the Exit of the Helium Purification System in HTR-PM

2018 ◽  
Vol 2018 ◽  
pp. 1-12 ◽  
Author(s):  
Mengqi Lou ◽  
Liguo Zhang ◽  
Feng Xie ◽  
Jianzhu Cao ◽  
Jiejuan Tong ◽  
...  
Keyword(s):  
High Temperature ◽  
Detection Efficiency ◽  
Primary Circuit ◽  
Source Terms ◽  
Primary Loop ◽  
Monitoring Instrument ◽  
Purification System ◽  
Design Values ◽  
Under Construction ◽  
High Temperature Gas

After the successful construction and operation experience of the 10 MW high-temperature gas-cooled reactor (HTR-10), a high-temperature gas-cooled pebble-bed modular (HTR-PM) demonstration plant is under construction in Shidao Bay, Rongcheng City, Shandong province, China. An online gross γ monitoring instrument has been designed and placed at the exit of the helium purification system (HPS) of HTR-PM and is used to detect the activity concentration in the primary circuit after purification. The source terms in the primary loop of HTR-PM and the helium purification process were described. The detailed configuration of the gross γ monitoring instrument was presented in detail. The Monte Carlo method was used to simulate the detection efficiency of the monitoring system. Since the actual source terms in the primary loop of HTR-PM may be different than the current design values, a sensitivity analysis of the detection efficiency was implemented based on different relative proportions of the nuclides. The accuracy and resolution of the NaI(Tl) detector were discussed as well.

Safety Study of Primary Loop System of Civil Marine Nuclear Power Plant

2014 ◽  
Vol 541-542 ◽  
pp. 916-921 ◽  
Author(s):  
Li Xu ◽  
Ru Chao Deng ◽  
Chu Xu ◽  
Di Zhang ◽  
Chen Xing Sheng
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Comprehensive Evaluation ◽  
Environmental Parameters ◽  
Loop System ◽  
Injection System ◽  
Safety Study ◽  
Primary Loop ◽  
Control Rods

For evaluate the risk of civil marine nuclear power plant, through the searching related standards for ship, external environmental parameters that the nuclear ship should be suited was found. Based on the characteristics of power plant of civil nuclear-powered ship, the hierarchy system of primary loop system was established and corresponding indicator marking criteria were formulated for the risk assessment. The result shows that the Reactor Safety Injection System (RIS), the Reactor Boron and the Water Supply System (REA), the Control Rods and the Hull of Fuel Canning are the key risk factors in the primary loop system. Finally, the comprehensive evaluation was carried out for collision, stranding and swing of multi-degree of freedom, and put forward relative countermeasures to cope with the possible risks based on the comprehensive evaluation and combined with the literatures.

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