Basic verification of THACS for sodium-cooled fast reactor system analysis

2015 ◽  
Vol 76 ◽  
pp. 1-11 ◽  
Author(s):  
Zaiyong Ma ◽  
Nina Yue ◽  
Meiyin Zheng ◽  
Benxue Hu ◽  
Guanghui Su ◽  
...  
Keyword(s):  
Fast Reactor ◽  
System Analysis ◽  
Reactor System

Development and application of 3D pool-type sodium cooled fast reactor system analysis program

2021 ◽  
pp. 104027
Author(s):  
Peng Du ◽  
Qingwen Xiong ◽  
Jianqiang Shan ◽  
Jian Deng ◽  
Wei Chen ◽  
...  
Keyword(s):  
Fast Reactor ◽  
System Analysis ◽  
Reactor System ◽  
Analysis Program ◽  
Pool Type

scholarly journals Development of Advanced Radiation Resistant ODS Steel for Fast Reactor System Applications

2015 ◽  
Vol 03 (03) ◽  
pp. 125-128 ◽  
Author(s):  
Tae Kyu Kim ◽  
Sanghoon Noh ◽  
Suk Hoon Kang ◽  
Hyun Ju Jin ◽  
Ga Eon Kim
Keyword(s):  
Fast Reactor ◽  
Reactor System ◽  
Ods Steel ◽  
Radiation Resistant

Performance of Sodium Natural Circulation Loop for Passvie Decay Heat Removal

2008 ◽  
Author(s):  
Hae-Yong Jeong ◽  
Kwi-Seok Ha ◽  
Won-Pyo Chang ◽  
Yong-Bum Lee ◽  
Dohee Hahn ◽  
...  
Keyword(s):  
Fast Reactor ◽  
System Analysis ◽  
Natural Circulation ◽  
Heat Removal ◽  
Circulation Loop ◽  
Ambient Atmosphere ◽  
Steady State Condition ◽  
Decay Heat ◽  
Natural Circulation Loop ◽  
Test Loop

The Korea Atomic Energy Research Institute (KAERI) is developing a Generation IV sodium-cooled fast reactor design equipped with a passive decay heat removal circuit (PDRC), which is a unique safety system in the design. The performance of the PDRC system is quite important for the safety in a simple system transient and also in an accident condition. In those situations, the heat generated in the core is transported to the ambient atmosphere by natural circulation of the PDRC loop. It is essential to investigate the performance of its heat removal capability through experiments for various operational conditions. Before the main experiments, KAERI is performing numerical studies for an evaluation of the performance of the PDRC system. First, the formation of a stable natural circulation is numerically simulated in a sodium test loop. Further, the performance of its heat removal at a steady state condition and at a transient condition is evaluated with the real design configuration in the KALIMER-600. The MARS-LMR code, which is developed for the system analysis of a liquid metal-cooled fast reactor, is applied to the analysis. In the present study, it is validated that the performance of natural circulation loop is enough to achieve the required passive heat removal for the PDRC. The most optimized modeling methodology is also searched for using various modeling approaches.

System reliability: An example of nuclear reactor system analysis

1984 ◽  
Vol 7 (2) ◽  
pp. 89-121 ◽  
Author(s):  
R. Coudray ◽  
J.M. Mattei
Keyword(s):  
System Reliability ◽  
System Analysis ◽  
Nuclear Reactor ◽  
Reactor System

scholarly journals TOKAMAK REACTOR SYSTEM ANALYSIS CODE FOR THE CONCEPTUAL DEVELOPMENT OF DEMO REACTOR

2008 ◽  
Vol 40 (1) ◽  
pp. 87-92 ◽  
Author(s):  
Bong-Guen Hong ◽  
Dong-Won Lee ◽  
Sang-Ryul In
Keyword(s):  
Conceptual Development ◽  
System Analysis ◽  
Reactor System ◽  
Tokamak Reactor

scholarly journals Scram and nonlinear reactor system seismic analysis for a liquid metal fast reactor

1976 ◽  
Vol 38 (3) ◽  
pp. 555-566 ◽  
Author(s):  
A. Morrone ◽  
A.N. Nahavandi ◽  
W.G. Brussalis
Keyword(s):  
Liquid Metal ◽  
Fast Reactor ◽  
Seismic Analysis ◽  
Reactor System

Allegro: The European Gas Fast Reactor Demonstrator Project

2009 ◽  
Author(s):  
Christian Poette ◽  
Vale´rie Brun-Magaud ◽  
Franck Morin ◽  
Jean-Franc¸ois Pignatel ◽  
Richard Stainsby ◽  
...  
Keyword(s):  
High Temperature ◽  
Fast Reactor ◽  
Heat Removal ◽  
Reactor System ◽  
Large Temperature ◽  
The Core ◽  
Intermediate Heat Exchanger ◽  
Current Design ◽  
Ceramic Fuel ◽  
High Temperature Components

In the Gas Fast Reactor development plan, ALLEGRO is the first necessary step towards the electricity generating prototype GFR. The ALLEGRO start of operation is planned by 2020. This needs to define all design options in 2010 and to start detailed design studies in 2013. ALLEGRO is a low power Gas Cooled Fast Reactor studied in the European framework. It is a loop type, non electricity generating reactor. Its power is about 80 MW. Several objectives are assigned to ALLEGRO. At first, it will demonstrate the viability of the GFR reactor system, no reactor of this type having been built in the past. Most of the GFR architecture, materials and components features are considered at reduced scale in ALLEGRO, excluding the energy conversion system. ALLEGRO will rely on the same safety options as the reactor system. In addition, the ALLEGRO core will allow the progressive qualification of the GFR ceramic fuel, with the possibility to load some ceramic carbide or nitride sub-assemblies in a first MOX core, with SiC/SiCf cladding and wrappers. When such unit test will be considered convincing enough, the diagrid and circuits are designed to accept full high temperature ceramic cores. The core neutrons can also be used to irradiate structural materials with fast neutron spectrum and in a large temperature range. The core can also include innovative irradiation fuel devices (samples or full bundles) for other reactor systems. Finally, branches on the main intermediate heat exchanger will allow the testing and validation of high temperature components and processes. The pre-conceptual design of ALLEGRO is shared between European partners through the GCFR 6th R&D Framework Program. After recalling the role of the European partners in the different design and safety tasks, the paper will give an overview of the current design with recent progresses in various areas like: • Core design and neutron performances, • The design of experimental advanced ceramic GFR fuel sub-assemblies included in several locations of the MOX core, • Fuel handling principles and solutions, • System design and global reactor architecture which is largely influenced by the Decay Heat Removal strategy (DHR) for depressurized accidents.

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