scholarly journals CFD Analysis of a Decay Tank and a Siphon Breaker for an Innovative Integrated Passive Safety System for a Research Reactor

2017 ◽  
Vol 2017 ◽  
pp. 1-9
Author(s):  
Kwon-Yeong Lee ◽  
Hyun-Gi Yoon ◽  
Dong Kyou Park
Keyword(s):  
Research Reactor ◽  
Safety System ◽  
Integrated System ◽  
Severe Accident ◽  
Passive Safety ◽  
Tank Model ◽  
Passive Safety System ◽  
Computational Fluid Dynamics Analysis ◽  
New Type

An innovative integrated passive safety system for a research reactor is proposed in this study to improve the safety of the research reactor. This integrated system has three functions in the facility as a decay tank, siphon breaker, and long-term cooling tank. This paper also deals with the process of designing and optimizing the decay tank and the siphon breaker of the integrated passive safety system. At first, the decay tank was designed and improved step by step, while considering the computational fluid dynamics analysis results. Consequently, we could satisfy the design requirements of the decay tank. In addition, the performance of a new type of siphon breaker that was installed in the final decay tank model was tested. We designed an 18-inch diameter siphon breaker at the top of the decay tank’s third section, and we could observe the breaking of the siphon that prevented the occurrence of a severe accident in the research reactor. By locating the siphon breaker at the third section of the decay tank, we could also use the coolant of the front three sections for long-term cooling of the research reactor.

ANALYSIS OF THE EFFECT OF PASSIVE SAFETY SYSTEM ON THE INTEGRITY OF THE CONTAINMENT IN CONDITIONS OF SEVERE ACCIDENT

2012 ◽  
Vol 13 (1-4) ◽  
pp. 9-26
Author(s):  
Alexander S. Balashevsky ◽  
Vladimir A. Gerliga ◽  
Dmitriy V. Shevielov ◽  
Igor I. Sviridenko
Keyword(s):  
Safety System ◽  
Severe Accident ◽  
Passive Safety ◽  
Passive Safety System

scholarly journals Simulation of the Westinghouse AP1000 Response to SBLOCA Using RELAP/SCDAPSIM

2014 ◽  
Vol 2014 ◽  
pp. 1-9 ◽  
Author(s):  
Ayah Elshahat ◽  
Timothy Abram ◽  
Judith Hohorst ◽  
Chris Allison
Keyword(s):  
Driving Forces ◽  
Natural Circulation ◽  
Safety System ◽  
Operating Conditions ◽  
Severe Accident ◽  
Passive Safety ◽  
System Component ◽  
Pressurized Water ◽  
Loss Of Coolant Accident ◽  
Accident Conditions

Great interest is given now to advanced nuclear reactors especially those using passive safety components. The Westinghouse AP1000 Advanced Passive pressurized water reactor (PWR) is an 1117 MWe PWR designed to achieve a high safety and performance record. The AP1000 safety system uses natural driving forces, such as pressurized gas, gravity flow, natural circulation flow, and convection. In this paper, the safety performance of the AP1000 during a small break loss of coolant accident (SBLOCA) is investigated. This was done by modelling the AP1000 and the passive safety systems employed using RELAP/SCDAPSIM code. RELAP/SCDAPSIM is designed to describe the overall reactor coolant system (RCS) thermal hydraulic response and core behaviour under normal operating conditions or under design basis or severe accident conditions. Passive safety components in the AP1000 showed a clear improvement in accident mitigation. It was found that RELAP/SCDAPSIM is capable of modelling a LOCA in an AP1000 and it enables the investigation of each safety system component response separately during the accident. The model is also capable of simulating natural circulation and other relevant phenomena. The results of the model were compared to that of the NOTRUMP code and found to be in a good agreement.

Code validation on a passive safety system test with the SMART-ITL facility

2016 ◽  
pp. 1-8
Author(s):  
Byong Guk Jeon ◽  
Yeon-Sik Cho ◽  
Hwang Bae ◽  
Yeon-Sik Kim ◽  
Sung-Uk Ryu ◽  
...  
Keyword(s):  
Safety System ◽  
Passive Safety ◽  
Code Validation ◽  
Passive Safety System

Assessment of passive safety system of a Small Modular Reactor (SMR)

2016 ◽  
Vol 98 ◽  
pp. 191-199 ◽  
Author(s):  
Hassan Nawaz Butt ◽  
Muhammad Ilyas ◽  
Masroor Ahmad ◽  
Fatih Aydogan
Keyword(s):  
Safety System ◽  
Passive Safety ◽  
Small Modular Reactor ◽  
Passive Safety System

The Development of the Evolutionary BWR (AB1600)

2008 ◽  
Author(s):  
Akira Murase ◽  
Mikihide Nakamaru ◽  
Ryoichi Hamazaki ◽  
Masahiko Kuroki ◽  
Munetaka Takahashi
Keyword(s):  
Fuel Cycle ◽  
Safety System ◽  
Safety Performance ◽  
Passive Safety ◽  
Main Role ◽  
Core Diameter ◽  
The Core ◽  
Passive Safety System ◽  
Bundle Size ◽  
Near Term

Considering the delay of the first breeding reactor (FBR), it is expected that the light water reactor will still play the main role of the electric power generation in the 2030’s. Accordingly, Toshiba has been developing a new conceptual ABWR as the near-term BWR. We tentatively call it AB1600. The AB1600 has introduced the hybrid active/passive safety system in order to have independent countermeasure for severe accidents and better probability of core damage frequency (CDF) considered external events such as earthquake. On the other hand, we have another goal of the AB1600, which is to retain the safety performance superior or equivalent to the current ABWR without deterioration of economy. In order to achieve both economy and safety performance, we have optimized the safety system configuration of the AB1600 by partly introducing passive safety system to design basis event (DBEs). At the same time, we have adopted the simplification of the overall plant systems in order to improve economy. In order to reduce capital cost, to shorten refueling period and to reduce maintenance effort, the AB1600 introduces the large fuel bundle size. The bundle size is 1.2 times as large as that of the ABWR and the fuel rod array is 12 by 12. And then by progressing the core design, we can reduce the number of reactor internal pumps (RIPs) to eight from the current ABWR of ten. The core power density, the number of fuel bundles, and the core diameter of AB1600 are decided in order to achieve 24 months fuel cycle length on the condition with below 5wt% enrichment of fuel and with eight RIPs.

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