scholarly journals An Experimental Study on the Smoke Behavior and Ensuring the Safety of Staircases in a Station Building During a Fire-Air Current Control in an Underground Station by a Passive Safety System-

2007 ◽  
Vol 26 (1) ◽  
pp. 9-42 ◽  
Author(s):  
Takeshi Tokunaga ◽  
Kenji Amano ◽  
Daisuke Oiwa ◽  
Seiji Uchiyama ◽  
Masayuki Mizuno ◽  
...  
Keyword(s):  
Experimental Study ◽  
Current Control ◽  
Safety System ◽  
Passive Safety ◽  
Passive Safety System ◽  
Underground Station

scholarly journals An Experimental Study on Flow Distributor Performance with Single-Train Passive Safety System of SMART-ITL

2016 ◽  
Vol 25 (4) ◽  
pp. 124-132
Author(s):  
Sung Uk Ryu ◽  
Hwang Bae ◽  
Jin Hwa Yang ◽  
Byong Guk Jeon ◽  
Eun Koo Yun ◽  
...  
Keyword(s):  
Experimental Study ◽  
Safety System ◽  
Passive Safety ◽  
Passive Safety System ◽  
Flow Distributor

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.

Preliminary LOCA Analysis of Heating-Reactor of Advanced Low-Pressurized and Passive Safety System (HAPPY)

2018 ◽  
Author(s):  
Mian Xing ◽  
Zhaocan Meng ◽  
Xiaotao Liao ◽  
Canhui Sun ◽  
Shuming Zhang ◽  
...  
Keyword(s):  
Conceptual Design ◽  
District Heating ◽  
Central Research Institute ◽  
Safety System ◽  
Passive Safety ◽  
Central Research ◽  
Pressurized Water ◽  
Design And Optimization ◽  
Passive Safety System ◽  
Safety Features

SPICRI (State Power Investment Central Research Institute) is developing a new conceptual design of heating-reactor, named Heating-reactor of Advanced low-Pressurized and Passive safetY system (HAPPY), which is targeted for the district heating, desalination of seawater, and other heat applications. It is a 200MWth two-loop low-pressurized water reactor with low thermal parameters. The whole reactor vessel is deployed inside a shielding and cooling pool with thermal insulation measure. The conceptual design of HAPPY is described in this paper, including the design criteria, safety features, main parameters and main components. A preliminary safety analysis is carried out to provide a reference for the design and optimization of HAPPY. In this paper, four different LOCA analyses are described and compared. The results show that the current design can deal well with all the selected LOCA scenarios and the effectiveness of the safety systems is proved.

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