Capability of RELAP5 code to simulate the thermal-hydraulic characteristics of open natural circulation

2017 ◽  
Vol 109 ◽  
pp. 612-625 ◽  
Author(s):  
Xiaofan Hou ◽  
Zhongning Sun ◽  
Wenjing Lei
Keyword(s):  
Natural Circulation ◽  
Hydraulic Characteristics ◽  
Relap5 Code

Experimental and Calculated Investigation of a Natural Circulation Loop’s Thermal-Hydraulic Characteristics

2019 ◽  
Vol 66 (7) ◽  
pp. 477-490 ◽  
Author(s):  
V. V. Yagov ◽  
N. O. Zubov ◽  
O. N. Kaban’kov ◽  
L. A. Sukomel
Keyword(s):  
Natural Circulation ◽  
Hydraulic Characteristics

Conceptual Design and Thermal-Hydraulic Characteristics of Natural Circulation Boiling Water Reactors

1988 ◽  
Vol 82 (2) ◽  
pp. 147-156 ◽  
Author(s):  
Yoshiyuki Kataoka ◽  
Hiroaki Suzuki ◽  
Michio Murase ◽  
Isao Sumida ◽  
Tetsuo Horiuchi ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Natural Circulation ◽  
Boiling Water ◽  
Boiling Water Reactors ◽  
Hydraulic Characteristics ◽  
Water Reactors

Numerical Study of the Gas-Steam Transient Behavior in the Integrated Pressurizer

2013 ◽  
Author(s):  
Lei Wu ◽  
Haijun Jia ◽  
Yang Liu
Keyword(s):  
Numerical Study ◽  
Natural Circulation ◽  
Transient Behavior ◽  
Pressure Change ◽  
Liquid Volume ◽  
Liquid Temperature ◽  
Analysis Model ◽  
Transient Characteristics ◽  
New Energy ◽  
Relap5 Code

The integrated gas-steam pressurizer stabilizes the pressure by compressing the gas and steam mixture. It has attracted much attention because of its simple structure, eliminating heating and spraying of equipment, and preventing the liquid boiling. The NHR series developed by Institute of Nuclear and New Energy Technology in Tsinghua University uses the integrated gas-steam pressurizer. The major loop thermal parameters in NHR series increased progressively, which made it suitable for heating, industrial steam supply and seawater desalinization. In order to ensure the safety of the NHR series major loop system and guarantee the natural circulation capability of the system under high temperature and pressure, the researches on the gas-steam transient characteristics of the integrated gas-steam pressurizer is needed. This paper is mainly about study on transient characteristics of the gas-steam typed pressurizer using the Relap5 code. The classic experiment on the pressure behavior of gas-steam pressurizer during the in-surge performed at MIT is considered as reference objects, and the analysis model is established by using Relap5 code. By comparing the computing results with the MIT experiment data about pressure-time, the applicability of Relap5 code for forecasting the transient behavior of the gas-steam (nitrogen) pressurizer has been verified. The results show that Relap5 code can effectively track the transient behavior of the pressure in the gas-steam pressurizer. In addition, the transient characteristics of the integrated gas-steam pressurizer in the NHR series have been studied. It is founded that the pressure and the liquid temperature adjoining to the pressurizer lag behind the power change in natural circulation loop with integrated gas-steam pressurizer, and the liquid temperature adjoining to the pressurizer and the liquid volume under the pressurizer are the main factors determining the pressure change.

scholarly journals Evaluation of the Potential for Containment Bypass due to Steam Generator Tube Rupture in VVER-1000/V320 Reactor during Extended SBO sequence using SCDAP/RELAP5 code

2021 ◽  
Vol 9 (4) ◽  
pp. 9-15
Author(s):  
Van Thai Nguyen ◽  
Manh Long Doan ◽  
Chi Thanh Tran
Keyword(s):  
Steam Generator ◽  
Natural Circulation ◽  
Severe Accident ◽  
Pressure Relief ◽  
Plant Behavior ◽  
Pressure Relief Valves ◽  
Station Blackout ◽  
Coolant System ◽  
Relap5 Code ◽  
Tube Failure

A severe accident-induced of a Steam Generator (SG) tube releases radioactivity from the Reactor Coolant System (RCS) into the SG secondary coolant system from where it may escape to the environment through the pressure relief valves and an environmental release in this manner is called “Containment Bypass”. This study aims to evaluate the potential for “Containment Bypass” in VVER/V320 reactor during extended Station Blackout (SBO) scenarios that challenge the tubes by primarily involving a natural circulation of superheated steam inside the piping loop and then induce creep rupture tube failure. Assessments are made of SCDAP/RELAP5 code capabilities for predicting the plant behavior during an SBO event and estimates are made of the uncertainties associated with the SCDAP/RELAP5 predictions for key fluid and components condition and for the SG tube failure margins. 

Effects of Rolling on Characteristics of System Under Forced Circulation and Natural Circulation

2020 ◽  
Author(s):  
Rong Cai ◽  
Nina Yue ◽  
Hongyu Fang ◽  
Baowen Chen ◽  
Lili Liu ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Natural Circulation ◽  
Thermal Parameters ◽  
Reactor System ◽  
Hydraulic Characteristics ◽  
Forced Circulation ◽  
Rolling Condition

Abstract The marine nuclear power plant operating in the marine environment has complicated motion under the influence of wind and waves. The movement of marine nuclear power plant will affect the thermal-hydraulic characteristics of its nuclear reactor system. Compared with other typical motion conditions, the effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system are the most complex. In order to study the effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system, a thermal-hydraulic system code for motion conditions named STAC was developed. The STAC code was verified by the experiments conducted in Japan. The effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system under forced circulation and natural circulation are studied with the STAC code. The simulation results show that the thermal parameters of the reactor system under rolling condition fluctuate periodically. The fluctuation period of the thermal parameters of the core is half of the rolling period, and the fluctuation periods of other thermal parameters are the same as the rolling period. The effect of rolling condition on thermal-hydraulic parameters under forced circulation is smaller than that under natural circulation. The fluctuation amplitudes of the thermal parameters increase with the angle amplitude of the rolling condition. There is a rolling period with the smallest fluctuation amplitude. Under the rolling condition with short period, the fluctuation amplitudes of the thermal parameters increase and their average values change rapidly as the rolling period decreases. Under the rolling condition with large period, the fluctuation amplitudes of the thermal parameters increase with the rolling period, and they tend to fixed values.

Preliminary investigation of natural circulation stability in FASSIP-01 experimental facility using RELAP5 code

2018 ◽  
Author(s):  
Anhar R. Antariksawan ◽  
Surip Widodo ◽  
Mulya Juarsa ◽  
Giarno ◽  
M. Hadi Kusuma ◽  
...  
Keyword(s):  
Natural Circulation ◽  
Preliminary Investigation ◽  
Experimental Facility ◽  
Relap5 Code
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