FIRST WALL RISK ANALYSIS FOR A LOSS OF COOLANT ACCIDENT IN AN EXPERIMENTAL FUSION REACTOR

A three dimensional computation fluid dynamics (CFD) code, GASFLOW, is applied to analyze the hydrogen risk for Qinshan-II nuclear power plant (NPP). In this paper, the effect of spray modes on hydrogen risk in the containment during a large break loss of coolant accident (LBLOCA) is analyzed by selecting three different spray strategies, that is, without spray, with direct spray and with both direct and recirculation spray. A strong effect of spray modes on hydrogen distribution is observed. However, the efficiency of the passive auto-catalytic recombiners (PAR) is not substantially affected by spray modes. The hydrogen risk is significantly increased by the direct spray, while the recirculation spray has minor effect on it. In order to simulate more precisely the processes involved in the PAR operation, a new PAR model is developed using CFD approach. The validation shows that the results obtained by the model agree well with the experimental results.

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Development of fatigue life criteria for experimental fusion reactor first-wall structures

Nuclear Engineering and Design ◽

10.1016/0029-5493(80)90129-6 ◽

1980 ◽

Vol 58 (2) ◽

pp. 283-299 ◽

Cited By ~ 4

Author(s):

R.E. Nickell ◽

E.P. Esztegar

Keyword(s):

Fatigue Life ◽

Fusion Reactor ◽

First Wall ◽

Wall Structures ◽

Experimental Fusion

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Stress Analysis of HCPB BB under Ex-Vessel LOCA Condition

Journal of Physics Conference Series ◽

10.1088/1742-6596/2108/1/012088 ◽

2021 ◽

Vol 2108 (1) ◽

pp. 012088

Author(s):

Mengdi Dai ◽

Xiaomo Wang

Keyword(s):

Stress Distribution ◽

Stress Field ◽

Stress Analysis ◽

Cross Section ◽

Maximum Stress ◽

Fusion Reactor ◽

Vacuum Vessel ◽

Loss Of Coolant Accident ◽

Loss Of Coolant ◽

Size Dimension

Abstract Helium Cooled Pebble Bed Breeding Blanket (HCPB BB) is a kind of concept for the European demonstration fusion reactor (DEMO). The blanket attachment system plays an important role in the mechanical connection of the BB and vacuum vessel. Typically, the mechanical and thermal loads should meet the requirement to avoid collapse of the system with off-normal conditions, e.g., under ex-vessel Loss of Coolant Accident (LOCA. This paper investigates the loading requirement corresponding to the maximum stress that can sustain to avoid the LOCA condition. Firstly, a model of the BB is constructed using SolidWorks. Then, stress analysis is carried out based on the cross section of the blanket. Through simulation, the critical condition for the LOCA case and the maximum stress value for the model are obtained. According to the relevant size dimension from the reference, the blanket’s cross section is drawn, and one can get the stress field under the ex-vessel LOCA through stress analysis. The stress distribution under the ex-vessel LOCA condition is simulated to find out the maximum stress field that the blanket can sustain through this paper. The significance is to predict the possible conditions leading to an accident and find possible methods to avoid them.

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